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KR0000240 KAERI/AR-561/2000 Degradation of fastener in reactor internal of PWR 3.1/40

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Page 1: 3.1/40 - International Nuclear Information System · 2004. 12. 24. · damage nuclear fuel and limits the operation of nuclear reactor. In foreign reactors operated more than 10 years,

KR0000240

KAERI/AR-561/2000

Degradation of fastener in reactor internal of PWR

3.1/40

Page 2: 3.1/40 - International Nuclear Information System · 2004. 12. 24. · damage nuclear fuel and limits the operation of nuclear reactor. In foreign reactors operated more than 10 years,

Please be aware that all of the Missing Pages in this document wereoriginally blank pages

Page 3: 3.1/40 - International Nuclear Information System · 2004. 12. 24. · damage nuclear fuel and limits the operation of nuclear reactor. In foreign reactors operated more than 10 years,

1 9 9 9 ^

2000. 3. 15.

Page 4: 3.1/40 - International Nuclear Information System · 2004. 12. 24. · damage nuclear fuel and limits the operation of nuclear reactor. In foreign reactors operated more than 10 years,

J9L

II.

17]

in.

. Baffle/Formerlr^S-

—^l lx l^ i 7&, control rod guide tube split pin-S: Alloy X-750, core support

sys tem^^ A286 *§•*]

^ 71 Til ^ - ^

IV. *-8-7j|3 g

7V1-71 ?Vol lOldal ^71

7]

- ii -

Page 5: 3.1/40 - International Nuclear Information System · 2004. 12. 24. · damage nuclear fuel and limits the operation of nuclear reactor. In foreign reactors operated more than 10 years,

SUMMARY

I. Title : Degradation of fastener in reactor internal of PWR

II. Objectives

Main component degraded in reactor internal structure of PWR is fastener

such as bolts, stud, capscrew, and pins. The failure of these components may

damage nuclear fuel and limits the operation of nuclear reactor. In foreign

reactors operated more than 10 years, an increasing number of incidents of

degraded thread fasteners have been reported. The degradation of these

components impair the integrity of reactor internal structure and limit the life

extension of nuclear power plant. To solve the problem of fastener failure, the

incidents of failure and main mechanisms should be investigated. The purpose

of this stat-of-the-art report is to investigate the failure incidents and

mechanisms of fastener in foreign and domestic PWR and make a guide to

select a proper materials.

III. Scope

There is no intent to describe each event in detail in this report. Thisreport covers the failures of fastener and damage mechanisms reported by thelicensees of operating nuclear power plants and the applicants of plantsconstructed after 1964. This information is derived from pertinent licenseeevent reports, reportable occurrence reports, operating reactor eventmemoranda, failure analysis reports, and other relevant documents.

- in -

Page 6: 3.1/40 - International Nuclear Information System · 2004. 12. 24. · damage nuclear fuel and limits the operation of nuclear reactor. In foreign reactors operated more than 10 years,

CONTENTS

Chapter 1. Introduction 1

Chapter 2. ASME Code for reactor internal fastener 2

Chapter 3. Structure of reactor internal and fastener 2

Section 1. Barrel/Former 2

Section 2. Control rod guide tube 4

Section 3. Thermal shield 4

Chapter 4. Accidents of fastener failure 5

Chapter 5. Suggestion for preventing fastener degradation 6

Chapter 7. References 7

Chapter 7. Properties of fastener materials 38Section 1. Type 316 stainless steelSection 2. X-750Section 3. A286

Appendix : ASME specification for fastener materials 53

- iv -

Page 7: 3.1/40 - International Nuclear Information System · 2004. 12. 24. · damage nuclear fuel and limits the operation of nuclear reactor. In foreign reactors operated more than 10 years,

TJI^D •

ouniniciry m

sj. ^jc^i 2

Barrel/Former 2

Control rod guide tube 4

Thermal shield 4

5

^ • ^ • ^ l ^ ^ T-fl-^ 6

n

S.AA _ ?8

316 iBfl^si i^ 7j-

X-750

A286

tfltb ASME Tf^ 53

- v -

Page 8: 3.1/40 - International Nuclear Information System · 2004. 12. 24. · damage nuclear fuel and limits the operation of nuclear reactor. In foreign reactors operated more than 10 years,

ii,

fetfl °]1- ^1^8r zp-sL irS., stud, capscrews, ^ ^

sat)-. o]l- < £ ; £ ^ f1^^ barrel/former^^-

control rod guide tubei && split pin^ ^ ^ « ]

oil- 1 : ^ 4 split pin^ol ^&S\T& ^717] ti

1982\1 IE Bulletin No. 82-025.^

Atomic Industrial Forum^ Materials Properties Council°1

. 5E*1- NRC^l^ Cracking of reactor vessel internals baffle former

bolts in foreign plants°H tfl«V Information Notice 98-11-i- ^asVfe -§- ir 41 :rp-

2:1-Si

- 1 -

Page 9: 3.1/40 - International Nuclear Information System · 2004. 12. 24. · damage nuclear fuel and limits the operation of nuclear reactor. In foreign reactors operated more than 10 years,

-g*H ^ ASME Boiler and

Pressure Vessel Code^l W %•&

Code 5

1. ASME Boiler & Pressure Vessel Code, Section VIII, Division 1

2. ASME Boiler & Pressure Vessel Code, Section HI, Division 1,

Subsection NC

3. ASME Boiler & Pressure Vessel Code, Section HI, Division 1,

Subsection ND

4. ASME Boiler & Pressure Vessel Code, Section XI

5. ASME Boiler & Pressure Vessel Code, Section III, Division 1,

Subsection NF 6. 1983 ASME Boiler & Pressure Vessel Code,

Section HI, Division 1, Subsection NB, Class 1 components

Ife NP-5769-&

1 ^ Barrel/Former

^ 316, 304, 347

zj- ^ - ^ 4 i ^ 7007fl(Point BeachH*] 110071]

(Farley)^5.^1-4. ^ ^ 4 ^ ^ ^ f ^ A } ^ 6]«D^

5X1020 n/cm2oa "fl 30-35%^

^ S f l^ preload7l- #«H-1-711 s|

Vcf. 1-^^r Barrel/Former assembly-2] RCCA guide tube,

Upper support column, Fuel pin, Lower support column

- 2 -

Page 10: 3.1/40 - International Nuclear Information System · 2004. 12. 24. · damage nuclear fuel and limits the operation of nuclear reactor. In foreign reactors operated more than 10 years,

4.

- Fuel degradation from baffle jetting

- Increased core bypass flow

- Potential failures of remaining bolts

- Impact of baffle plates on fuel assemblies

Westinghouse Owners Grouper * 1 ^ %v*l4io]H

Point beech 2, Farley 1, Ginna «fl tfl*H

Farleyl (1088711 ^ j * | 10867H

* m 2777fl # E . - § - S^ l§}^4 . Point Beach 2°iHfe 55/fl ^ - E .

head-to-shank^^^l^ ^ r ^ ^ ^ J L 728711 ^ M 97^7} -Efl7>

^ 6397H1- ^

1. ^

2tfl

2.

baffle plate-

o j ^ t downflowSJfSl upflowS.

^-^S) ^^-s] 900 MWe

316 ^Bll<?lslli 7 ^ ^ ^-^sf^cf. Fressenhim 2 <*IHfe 9607H f efl/cj 29

9607H ^ ^ A - ] 547HlAi M ° l ^ 3 s > ^ 4 . ^ ^ H Tihange 1A>^ ^ 4 1991\i°ll^ 2l7fl7> ;£•§-§• 7

o]]^ 377117]- ^ ^ - # 7}x)5L 5ial 537B7]-

316 ^31?

l 3164 y]

WWER 440^]

- 3 -

Page 11: 3.1/40 - International Nuclear Information System · 2004. 12. 24. · damage nuclear fuel and limits the operation of nuclear reactor. In foreign reactors operated more than 10 years,

Control rod guide tube

X-750°]

^ ^^l^-i upper core plated ^ ^ 4 control rod guide tube ^ ^-£-£ <£

^ K r ^^1 split pin ?1B|1 o]^ol 1978V! 1: ^ 4 0 . ^ ? 1 4 ^ P ^ S 2)-^^ i J l

s)3i 514. Guide tube1? 27fl5l ^o] ^^tf l q- ^^^61) 45}A^ 58-12471)^

spit pin°l $14- B&W7}- 1984^ ^ i i S spit pin^ 51^1- Verginia Power£]

Surry 1«H^ ^ 1 ^ « } ^ 4 .

Westinghouse^r X-750^] split pi

1093 °C^1^ 1*1 #, AlSi^elfe 704TC^^ 20*] ?> ^ ^ « > ^

-§-«fl, ^ ^ ° J ? l l i M 2 3C 6W!-g: ^ # * M 4 . Split pin^ ^ ^ # ^°}

4^-2}- ^r°l -S31* ^ ^ s f ^ c f : ci s ^ o . s x | ^ u|E6)] peening,

shoulder ^§^§-

shank-shoulder ^ i r €<ill*1 parabolic I S ^ ^ 2 . U | E . ^ torque^

SI-^4. 2L*V cf^-4 7Ev^ A}%)-s-4 7fl^S}^4.

- Decreased prong deflection

- Tolerances tightened

- Sensitive area polished

- Machining after final heat treatment

- Finer threads and larger shank diameter

- Obtaining shoulder by hot forging

- Use of water cooling after annealing

- Cold rolling of IGSCC sensitive areas

x _ 7 5 0 rfl lofl ^^>7}-^^ 316 i

Thermal shield

- 4 -

Page 12: 3.1/40 - International Nuclear Information System · 2004. 12. 24. · damage nuclear fuel and limits the operation of nuclear reactor. In foreign reactors operated more than 10 years,

^ ^°1M thermal shield^ 31*113 Si lEfl^- barreH] thermal shield

7} ^ Q z}4*l n ^ # ZL$ 5*11 4 4 ^ &4. 2 )2^ thermal shield 1:^1 tfl

*V £ ^ 1981 *d B&W Duke Powers Oconee l ^ ^ H lower internal

structured l-^&fe thermal shield* H^^}3L &•£ A286AS. all 2 3 1-^$

4.

long handled pole^l^f 7}% S 4 ^ ° 1 ^ 4 . lOVi^H

-ffe thermal shield I r ^ ^ ^ i ^ ^ f^^^> 5fl^^ 1000- ^sflA^ # ^ A ^ 40 ftol'* ^ ^ 45 MR/hrS

a 34 ^cV. ^ J f ^ H t ^-^ ^r^7], ^ ^ preload, ^ 3 * ^=.3]. 7EV^ 37}-;*] ^ ^ « V ^616|| ^jflX^ 4 ^ 0 ] l £ ^ $ t f . ojs- ^ ^

37flsi ^ ^ 7 1 ^ ^ * H ^ «i-i4 OIAOT-O] 7 i ^ 7 | . ^ - a s H ^ 3§1-711 s i 4

1.

y\. Borated-water leakage

4 . Wet or humid environment

4 . High preload

^\. Use of lubricant containing molybdenum disulfidePK Improper heat treatment of materials

2. 5z)^£] «M83lS!

7\. Flow-induced vibration

4 . Improper preload

3. Borated-water corrosion and erosion-corrosion- ]

- 5 -

Page 13: 3.1/40 - International Nuclear Information System · 2004. 12. 24. · damage nuclear fuel and limits the operation of nuclear reactor. In foreign reactors operated more than 10 years,

Borated-water leakage

4. Other threaded-fastener £)

7\. Improper heat treatment of materialsuf. Improper preload

^K Wrong material

5.

1. -

7}. Control rod guide tube support fastener (split pin)

*4. Baffle/former bolts

^K Core barrel and lower grid assembly bolts

7h Core barrel/thermal shield (2CE plants)

!-K Reactor instrumentation

qjoi- cfl*H

Bulletin No. 8

fet-l] 6 ] ^ ^ - reactor coolant pressure boundary closured

sealant compound^]- lubricant^ ^ ^ - t - «9^*1 ^l l^^V^^ Q

2. ^ 1 ^ - 1 : ^ ^ 7 l M - ^7^f7 l ^*> x]-^*!- ^ * H 4 closure seal system

3. Manway closure assembly^ stud^f -M-H-f- ^ ± * ] - J I ^-^r^^l-i- T * ! ^

°> *>JL closure seal^l ^ H ] *}/-fM-& ^*flAi # ^ 1 ^ ] ^ ^ "fl magnetic

particle° 1M- dye penetrant (nonmagnetic material) 33 *}••!• ^r^^f0^0!1 tb

Lawrence Livemore Nation Laboratory°?l^i <^ei 7\T] ^-#ofl tflsflAi Kiscc

- 6 -

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M 7 —

Page 15: 3.1/40 - International Nuclear Information System · 2004. 12. 24. · damage nuclear fuel and limits the operation of nuclear reactor. In foreign reactors operated more than 10 years,

", KAERl/TR-434/94

2. EUR 17694EN, "Effect of irradiation on water reactors internals", 1997.

3. Gary T. URQUHART, "Reactor internals repairs the simple approach

prevails", Proceedings of the international meeting on Nuclear Power Plant

Maintanence, Salt Lake City, Utah, March 23-27, 1986, 16.

4. NUREG-0943, "Threaded-fastener experience in Nuclear Power Plants",

1983.

- 8 -

Page 16: 3.1/40 - International Nuclear Information System · 2004. 12. 24. · damage nuclear fuel and limits the operation of nuclear reactor. In foreign reactors operated more than 10 years,

UPPER THERMAL SHIELD(60) 1 3/4 in.(4.4 cnODIA.

SURVEILLANCE HOLDERTUBE (12 per tube)3/4 in. (1.9 cm) DIA.

LOWER THERHAL SHIELD(96) 1 in.(2.5 cm) DIA.

FLOW DISTRIBUTOR(96) 1 in.(2.5 cm) DIA.

UPPER CORE BARRELJOINT (120)13/4 in. (4.4 cm) DIA.

LOWER CORE BARRELJOINT (108)13/4 In. (4.4 cm) DIA.

Fig. 1. B&W internal bolting

- 9

Page 17: 3.1/40 - International Nuclear Information System · 2004. 12. 24. · damage nuclear fuel and limits the operation of nuclear reactor. In foreign reactors operated more than 10 years,

Formers

Fig. 2. Bafle plates and formers of a pressurised water reactor.

- 10 -

Page 18: 3.1/40 - International Nuclear Information System · 2004. 12. 24. · damage nuclear fuel and limits the operation of nuclear reactor. In foreign reactors operated more than 10 years,

Table 1. Specified chemical composition of austenitic stainless steels employed

as bolts and fastener in internal structures of European PWR.

Z6CND17-12Cold Worked316

FranceZ2CND17-12Cold WorkedN controlled316FranceZ2CND17-12Cold Worked316

France316Cold Worked(SA 479)

UKX6CrNiMoTi17-12-2Cold Worked(1.4571)

Germany

C

0.03

0.08

0,035

0.030

0.040

0.080

0.060

Mn

2.0

2.0

2.0

2.0

2.0

Si

1.0

1.0

KO

1.0

1.0

s

0.03

0.03

0.03

0.03

0.02

P

0.035

0.035

0.040

0.045

0.035

Ni

10.0-14.0

11.5-12.5

10.0

14.0

10.0

14.0

10.5-13.5

Cr

16.0-18.0

17.0-18.2

16,0

19.0

16.0

*18.0

16.5-18.5

Mo

2.25-3.00

2.25-2.75

2.25-2.75

2.0

3.0

2.0

2.5

Nb

-

-

-

-

-

Ti

-

-

-

-

0.7

Co

0.20

0.20

0.20

0^25

0.20

Cu

1.0

1.0

To

-

N

-

0.08

0.08

0.10

-

B

-

-

-

-

-

Material Code

08Khl8N10T

KhN35VT(VD)

KhN77TJuR

14Khl7N2

10KhllN20T3R

N P 2

C

<

0.08

<

0.12

<

0.06

0.11

0.17

<

0.10

Mn

1.0

2.0

1.0

2.0

<0.6

<

0.8

<1.0

Si

<0.6

<0.6

<0.8

<1.0

s

<0.02

<o.o;<0.01

<0.007

<0.025

<0.02

P

<0.035

<0.03<

0.025

<0.015

<0.025

<0.020

Ni

9.0-11.0

34 -38

34-36

base

1.5•

2.518.0

-21.0

-100

Cr

17.0-19.0

14.0-16.0

19.0-22.0

16.0

18.0

10.0-12.5

Ti

>5C<0.6

1.1 -1.5

2.3-2.7

2.6-3.2

Al

0.55

0.95

W

2.8

3.5

Ce<

0.02

B

<0.01

0.008-

0.020

Fe

base

base

<4.0

base

base

Standards

GOST5632

GOST5632

GOST23304

GOST5632

GOST5949

GOST5632

GOST492

11

Page 19: 3.1/40 - International Nuclear Information System · 2004. 12. 24. · damage nuclear fuel and limits the operation of nuclear reactor. In foreign reactors operated more than 10 years,

Table 2. Specified mechanical properties of internal steels employed in the

internal structures of European PWR.

Materials

Z3CN 18-10N controlled304L(M3310)France304UK (SA182)304UK (SA240)X6CrNiNbl8-10Germany (1.4550}Z6CNDI7-12Cold Worked316 (M 3308)FranceZ2CND17-12Cold WorkedN controlled316 (M 3308)FranceZ2CND17-12Cold Worked316 (M 3308)France316Cold Worked(SA 479)UKX6CrNiMoTi17-12-2Cold Worked(1.4571)Germany

Product size

mm

F<30

30< F < 50

F<30

3CK F < 50

F<30

30< F < 50

F<50

F>50

Vield strength20°C (MPa)

>210

>205

>205

450 - 620

450 - 620

450 - 620

450 - 620

450 - 620

450 - 620

450 - 620

415 - 620

Tensilestrength

20°C (MPa)

>520

> 515

> 515

>655

>590

>655

>590

>655

>59O

>585

>586

Elongation20°C (%)

> 4 0

>30

S 4 0

> 3 0

> 3 0

S 3 0

30-67

>30

Reductionofarea20°C

(%)

> 5 0

> 6 0

> 6 0

> 6 0

ImpactCharpy U

(J/cm2)

> 12

> 12

> 12

> 12

Material Code

08Khl8N10T

KhN35VT(VD)

KhN77TJuR

14Khl7N2

10KhllN20T3R

N P 2

Rp02. MPa

> 196

£395

>490

<0.01

>835

>590

MPa

>490

>735

>835

> 1226

> 1080

>885

Standards

GOST 5632

GOST 5632

GOST 23304

GOST 5632

GOST 5949

GOST 5632

GOST 492

- 12 -

Page 20: 3.1/40 - International Nuclear Information System · 2004. 12. 24. · damage nuclear fuel and limits the operation of nuclear reactor. In foreign reactors operated more than 10 years,

Control rod drive- helical springs -

Hold down assembly- disc springs -

Upper alignment pins

Fuel- guide pins, springsCore internals- screws -

Lower alignment pins

Fig. 3. Inconel X-750 parts in PWR.

- 13 -

Page 21: 3.1/40 - International Nuclear Information System · 2004. 12. 24. · damage nuclear fuel and limits the operation of nuclear reactor. In foreign reactors operated more than 10 years,

Upper'support plate

Control rod'guide tube

Guide tubebottom plate

Upper coreplate

L , • . , J

Nut

Failure

Guide tubebottom plate

Variablethickness13/4-4 in.

portion

-Shoulder

Upper core plate

9-0443

9-0442

Fig. 4. Westinghouse control rod guide tube assembly and split pin. A typical

failure location in a split pin is also shown.

- 14

Page 22: 3.1/40 - International Nuclear Information System · 2004. 12. 24. · damage nuclear fuel and limits the operation of nuclear reactor. In foreign reactors operated more than 10 years,

UPPER CORE BARREL

LOWER CORE BARREL

SURVEILLANCE SPECIMENHOLDER TUBES

FLOW DISTRIBUTOR

-THERMAL SHIELD

Fig. 5. B&W thermal shield.

- 15 -

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THERMAL SHIELD LOWER SUPPORT

THERMALSHIELD

I 3/4

LOWER GRIDRINGFORGING

96-0.8" BOLTS(A286 SST)

ORIFICE FLOWHOLES

BARREL

0.030 TO 0.060INTERFERENCEFIT

U^—108 - 1.6" BOLTS

LOCKINGCLIPS

(ALL OTHER MATERIALS 304 SST)

Hg. 5. Continued.

- 16 -

Page 24: 3.1/40 - International Nuclear Information System · 2004. 12. 24. · damage nuclear fuel and limits the operation of nuclear reactor. In foreign reactors operated more than 10 years,

Table 3. PWR bolt failures - in reactor.

i

Component

Control Rod Guide Tube

FA screw for holddownspring clamp

Bolt Type(Material)

Support PinInconel X-750

Clamp Holddown Screws(Head separated from screw)Inconel 600

Failure Type, Causeand Corrective Action

IGSCCInadequate Heat Treatment

Plant

Beaver Vailey 1

Cook 2

Farley 1

North Anna 1

Point Beach 1

Point Beach 1

Point Beach 1

Salem 1

Surry 1

Trojan

4+ French Plants

Date

7/83

1/85

2/84

5/82

1/84

2/84

4/85

3/84

10/84

5/84

'82 and on

IGSCC

4+ Japanese p lan ts 82' and on

Surry 1+ 2 others

6/84

Core barre l screws Inconel X-750 IGSCC Bibl is 81

Page 25: 3.1/40 - International Nuclear Information System · 2004. 12. 24. · damage nuclear fuel and limits the operation of nuclear reactor. In foreign reactors operated more than 10 years,

Table 3. Continued.

i

CO

Component

Reactor Core ThermalShield

Bolt Type(Material)

Bol ts , A-286(SA 453 GR 660)

Core barrel to supportshield

Failure Type, Causeand Corrective Action

IGSCC, excess stress,large grain size dueto manufacturing tech-niqueReplaced with X750

Plant

Oconee 1

Date

10/81

studs and nuts.

Replaced with re-designedA-286

replaced wisame materi

th new designal

Oconee 2

Davis-Besse

Oconee 3

Davis-Besse

Crystal River 3

Rancho Seco

.ANO 1

Davis Besse

Rancho Seco

Rancho Seco

Crystal River 3

Rancho Seco

1/82

4/82

6/82

9/86

4/83

6/83

4/83

8/83

3/85

3/83

4/83

6/83

Page 26: 3.1/40 - International Nuclear Information System · 2004. 12. 24. · damage nuclear fuel and limits the operation of nuclear reactor. In foreign reactors operated more than 10 years,

Table 4. PWR bolt failure - ex reactor.

Component

Reactor Coolant Pump

Steam Generator

Pressurizer

Spent Fuel Pool Coolingpump discharge val ve

RTD* bypass loopisolation valve

Bolt Type(Material)

Pump headflange studs

Closure studs(SA-193 GRB7, AISI 4140)

Manway ClosureStuds (SA540 GRB24)

Manway Closure Studs

Manway Closure Studs

Manway Retaining Studs

Manway Cover studs (Alloysteel)

Studs(A-193 GRB6)(Type 416SS)

Body-to-bonnet studs(Carbon Steel)

Body-to-bonnet studs(A193 GRB7)

Body-to-bonnet studs

Failure Type, Causeand Corrective Action

Boric acid induced corrosion(actual or suspected)

IGSCC

Alloy steel

Plant

Calvert Cliff 1

Ft. Calhoun

Maine Yankee

Oconee 3

ANO 1

St. Lucie 1

St. Lucie 1

Date

11/80

5/80

3/82

82

82

4/77

1/78

Replaced with unspecified Maine Yankee 2/82material

North. Anna 1 4/83

Point Beach 1 11/82

Point Beach 2 11/82

* Resistance Temperature Detector

Page 27: 3.1/40 - International Nuclear Information System · 2004. 12. 24. · damage nuclear fuel and limits the operation of nuclear reactor. In foreign reactors operated more than 10 years,

Table 4. Continued.

Component

Reactor Coolant Pump

Service water pump

SW Pump packing glandhousing

Diesel generator blowerdischarge

Recirc. spray pumpsuction valve

Pressure d i f fe rent ia ltransmitter

Bol t Type(Material)

Diffuser to casing adaptercap screws

Diffuser adapter cap screws

Bolts

Hinge studs

Studs (Carbon steel)

Flange bolts

Valve operator supportStand bolts

Steel cadium plated Bolts

Pressurizer spray valve Body-to-bonnet studs

Expansion compensatingring in reactor vessel

Pressurizer PORV

Polar crane ra i l

Bolts

Gland retainer bolts

Hold-down cl ip bol ts

Failure Type, Causeand Corrective Action

High stress levelCl induced SCC, out ofspec, (cold worked vs.annealed)

Plant

Robinson 2

transmitter

Excess stress due todifferential thermalexpansion by mixing carbonsteel and ss

Main Yankee

Date

4/82

Unknown - replaced with ahigh strength material

N/A

Excess torque

Corrosion, replaced withSS

Unknown

Insufficient strengthreplaced with stronger bolts

Oxidation

North Anna 1

Rancho Seco

Rancho Seco

Surry 2

Calvert Cliff 1

Surry 2

Palisades

8/82

3/85

7/84

11/82

10/81

10/83

5/71

3/79

Excess stress

Uneven torque

high cycle fatigue

Palisades

McGuire 2

Rancho Seco

5/72

4/83

7/82

Page 28: 3.1/40 - International Nuclear Information System · 2004. 12. 24. · damage nuclear fuel and limits the operation of nuclear reactor. In foreign reactors operated more than 10 years,

Table 5. BWR bolt failures - ex reactor.

ComponentBolt Type(Material)

Cold leg safety in ject ion Body-to~bonnet studscheck valve

Cold leg safety in ject ion Body-to-bonnet studscheck valve

Pressurizer spray valve

Pressurizer motoroperated valve

Letdown Heat Exchange

Reactor Vessel Head

(carbon steel)

Body-to-bonnet studs

Body-to-bonnet studs

Flange studs

Studs (Parken'zed Coating)

Failure Type, Causeand Corrective Action

Boric acid induced corrosion(Actual or suspected)

i 1

Plant

Kewaunee

North Anna 1

Kewaunee

Yankee Rowe

Pal isades

Pal isades

Date

4/82

9/82

4/82

4/83

11/80

11/71

Page 29: 3.1/40 - International Nuclear Information System · 2004. 12. 24. · damage nuclear fuel and limits the operation of nuclear reactor. In foreign reactors operated more than 10 years,

Fig. 5. Continued.

CO

to

Component

Spring Can Hanger

Vacuum Breaker

Diesel Generator

Bol t Type(Material)

"Red Head"Concrete Expansion Bolts

Flathead mounting bolts

Manifold Bolt (Type 304SS)

Failure Type, Causeand Corrective Action

Degradation ofconcrete expansion bolts

Cyclic Shearing (SAE Grade8) Replaced with strongerAllen bolts

Possible Misapplication ofbolt Material replaced withType 316SS, unt i l Type 410obtained.

RCP

Fuel

Upper Guide

Assembly

Stud

Channel fastener toupper nozzle, InconelX750

Channel fastener to lowernozzle, Inconel X-750

N/A

IGSCC

IGSCC

Plant

Duane Arnold

Dresden 3

Grand Gul f

Date

3/82

8/84

8/83

Browns

Several

Several

Ferry 3 8/79

70 ies& 80 i

'83 -

es

'84

Page 30: 3.1/40 - International Nuclear Information System · 2004. 12. 24. · damage nuclear fuel and limits the operation of nuclear reactor. In foreign reactors operated more than 10 years,

Table 6. Incidents of stress corrosion of threaded fasteners.

Plants

LaCrosse (BWR)

Ginna

Haddam Neck

Surry 1

Surry 2

San Onofre 1

Midland 1

Year

reported

1970

1970

1973

1975

1975

1977

1979

Componentsand parts

Reactor vesselclosure studs(3.5-in. diameter)

Steam generatorsupport anchorstuds (1-3/8-in.diameter)

Steam generatorsupport anchorbolts (2-in.diameter)

Steam generatorsupport bolts

Steam generatorsupport bolts

Steam generatormanway studs

Reactor vesselskirt flange imbedanchor studs(2-1/2 in.diameter)

Materialsof parts

12% Cr marten-sitic stainlesssteel (ASTM-A-437-B4B)

Low alloy steel(AISI-4140)

Low alloy steel

Maraging steel(Vascomav n)

Maraging .(Vascomax 250)

Low alloy steel(AISI 4140)(A193-B7)

Low alloy steel(AISI-4140,4145)

Contributingfactors

(1)

(2)

(3)

(4)

(1)(2)

(1)(2)

(1)

(2)

Aqueous environmentduring outageImproper heat

treatment ofmaterialGalvanic actionresulting fromsilver platingbreakdownPretension

160 ksi pretensionHumid/wet borateciwater

PretensionWater leakage

Improper heattreatment ofmaterialExcessive preloadof 87-92 ksi

Correctiveaction

(1) Replaced with studs made fromA-540-B23, Class 4 material

(2) Augmented inservice inspec-tion ultrasonic testsurveillance

(1) Replaced with studs made fromA-490 material

(2) No pretension

(1) 24 of 256 bolts replaced(2) Pretension reduced on

replaced bolts(3) Microswitch installed on all

bolts for monitoring

Replaced with Cd-platedVascomax 250 bolts

Replaced with Cd-platedVascomax 250 bolts

8 studs replaced

(1) Remaining studs detensiontdto 6 ksi

(Z) Upper lateral supportinstalled on vessel

Page 31: 3.1/40 - International Nuclear Information System · 2004. 12. 24. · damage nuclear fuel and limits the operation of nuclear reactor. In foreign reactors operated more than 10 years,

Table 6. Continued.

PlantsYearreported

Componentsand parts

MateriaIsof parts

Contributingfactors

Correctiveaction

to

1

Arkansas 1 1978 Steam generatormanway closurestuds

1980 Steam generatormanway closurestuds

Oconee 3 1980 Steam generatormanway closurestuds (2-in.diameter)

Prairie 1980 Steam generatorIsland 1 • column support

bolts (1-1/2 in.dijmeter)

Prairie 1980 Steam generatorIsland 2 column support

bolts (1-1/2-in.diameter)

Rancho Seco 1980 Valve studs

O.C. Cook 1 1981 Main steamisolation valveinternals - studs

Low jlloy steel(AISI 1340)

Low alloy steel(AISI 4310)

Low alloy steel(SA-320, GradeL-13)(AISI-4340)

Maraging steel(Vascomax 250)(A538 grade B)

Maraging steel(Vascomax 250)(A538 grade B)

Stainless steelType 416(A-193-B6)

Low alloy steel(AISI 4340)

(1) Use of thread lub-ricant containingmolybdenum disul-fide

(2) Preload

(1) Use of thread lub-ricant containingmolybdenum disul-fide

(2) Trapped moisture

Excessive preload(1,400 "ft-lb torque)

Excessive preload(1,400 ft-lb torque)

Improper heat treatmentof material

(1) Primary steam(2) Possible use of

thread lubricantcontaining molyb-denum disulfide

(3) Possible over-torque

2 cracked studs replaced

3 cracked studs replaced

All studs replaced (threadlubricant containing molybdenumdisulfide was applied)

(1) Replaced with studs made fromsame material

(2) Pretension reduced

(1) Replaced with studs made fromsame material

(2) Pretension reduced

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Table 6. Continued.

PlantsYearreported

Componentsand parts

Materialsof parts

Contributingfactors

Correctiveaction

Oconee 1

Oconee 2

Palo Verde

Maine Yankee

1981 Reactor vesselinternals -thermal shieldbolts

1981 Reactor vesselinternals -thermal shieldbolts

1981 Piping restraintimbedded anchorbolts (1-1/2-in.diameter)

1982 Steam generatormanway clnsurestuds (l-i/2 in.diameter)

6-in. gate valvebonnet-to-bodystuds (5/8-in.diameter)

A-286 stainlesssteel

A-286 stainlesssteel

Low alloy steel(AISI 4140)(A-354 Grade BD)

Low alloy steel(SA540-B24)

Stainless steel

(1) Borated waterenvironment

(2) Preload of 32 ksiand 32 ksi bending

(1) Borated-waterenvironment

(21 Preload of 32 ksiand 32 ksi bending

Improper heat treatmentof material

(1) Gasket leakage ofborated water

(2) Use of Furmaniteseal ing compound ,

(3) Use of thread lub-ricant containingmolybdenumdisulfide

(4) Preload of 900 -1,100 ft-lb

Valve body-to-bonnetgasket leakage ofborated water

(1) Lower thermal shieldredesigned

(2) Use of Inconel X-750 studsand nuts

(1) Lower thermal shieldredesigned

(2) Use of Inconel X-750 studsand nuts

10 failed studs replaced withstuds of the same stock

(1) Proposed short-term actionreplace with AISI 4140 (A-196-B7) studs

(2) Proposed long-term action -use 17-4 PH studf.

Page 33: 3.1/40 - International Nuclear Information System · 2004. 12. 24. · damage nuclear fuel and limits the operation of nuclear reactor. In foreign reactors operated more than 10 years,

Table 7. Incidents of fatigue of threaded fasteners.

PlantsYearreported

Componentsjnd parts

MoteriaIsof parts

Contributingfactors

Correctiveaction

Big Rock Point 1064(BWR)

Yankee Rowe 1968

Palisades 1972

Reactor vesselinternals -thermal shieldbolts

Reactor vesselinternals -thermal shieldbol ts

vesselinternals - hold-down bolts forring shim (1/Z-in.diameter)

Typt> 31& stain-less steel(ASTM A-276)

flow-induced vibration Support and flow pattern modified

Type 316 stain- Flow-induced vibrationless steel

Type 301 stain-less steel

Improper torque

Clamp added to each thermalshield joint

(1) Broken bolts replaced(2) Proper torque and clearance

Page 34: 3.1/40 - International Nuclear Information System · 2004. 12. 24. · damage nuclear fuel and limits the operation of nuclear reactor. In foreign reactors operated more than 10 years,

Table 8. Incidents of borated-water corrosion of threaded fasteners.

Plants

St. Lucie

CalvertCliffs 1

Fort Calhoun

Arkansas 1

CalvertCliffs 2

Yearreported

1977

1978

1980

1980

1980

1981

1981

1981

1981

Componentsand parts

Steam generatormanway closurestuds (1-1/2-in.diameter)

Pressurizer man-way closure studs

Reactor coolantpump closure studs

Steam generatormanway studs

Reactor coolantpump closure studs(3-1/2-in.diameter)

Reactor coolantpump closure studs(3-1/2-in.diameter)

Steam generatormanway closurestuds

Reactor coolantpump closure studs

Pressurizer manwaystuds

Materialsof parts

Low carbon lowalloy steel(SA-540-B24)

Low carbon lowalloy steel(SA-540-BZ4)

Low alloy steel

Low alloy steel

Low alloy steel(A1S1 4140)(SA-193-B7)

Low alloy steel(AISI 4140)(SA-193-67)

Low alloy steel

Low alloy steel

Low alloy steel

Contributingfactors

Manway gasket leakageof borated water

Manway leakage ofborated water

Possible gasket leak-age of borated water

Gasket leakage ofborated water

Flexitallic flangegasket leakage

Closure gasket leak-age of borated water

Possible gasket leak-age of borated water

Seal leakage of bor-ated water

Correctiveaction

(1) 3 studs replaced(2) Gasket replaced

5 corroded studs replaced

27 studs replaced

11 studs replaced

9 studs replaced

Corroded studs replaced

Corroded studs replaced

12 studs replaced

2 studs replaced

Page 35: 3.1/40 - International Nuclear Information System · 2004. 12. 24. · damage nuclear fuel and limits the operation of nuclear reactor. In foreign reactors operated more than 10 years,

Table 8. Continued.

PlantsYearreported

Componentsand parts

Materialsof parts

Contributingfactors

Correctiveaction

D.C. Cook. 2 1981 Check valve bonnetbolts

Kewaunee 1981 8-in. motor-operated valvebody-to-bonnetstuds

Oconee 2 1981 Reactor coolantpump closure studs

Oconee 3 1981 Reactor coolantpump closure studs

Low alloy steel(AIS1 4110)(A-193-87)

Low alloy steel

Low alloy steel

Low alloy steel

Valve body-to-bonnetgasket leakage ofborated water

Valve body-to-bonnetgasket leakage of con-centrated (12%) boratedwater

Closure gasket leakageof borated water

Closure gasket leakageof borated water

All 12 studs replaced

Corroded studs replaced

1 stud replaced

1 stud replaced

Table 9. Incidents of erosion-corrosion of threaded fasteners.

PlantYearreported

Componentsand parts

Materialsof parts

Contributingfactors

Correctiveaction

Zion 1 1979 Chemical andvolume controlsystem valve bolts

Low alloy steel(AISI 4140)(A193-B7)

Valve gasket leakageof borated water

(1) Degraded bolts replaced(2) Valve bonnet, reassembled

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Table 10. Incidents of other types of degradation of threaded fasteners.

Plants

Sequoyah 1

Sequoyah 2

Arkansas 1

Pilgrim 1(SWR)

Surry 2

Vermont Yankee

Waterford

Yearreported

1977

1977

1980

1981

1981

1981

1981

Componentsand parts

Steam generatorsupport bolts(1-1/2-in.diameter)

Steam generatorsupport bolts(1-1/2-in.diameter)

Emergency feed-water turbinesteam inlet bolts

Valve limit-torqueoperator motorholddown bolts

Service water pumpimpeller capscrew

Valve limit-torqueoperator motormounting bolts

Reactor coolantpump support bolts

Materialsof parts

Carbon steel(C-1117)

Carbon steel

A-490 alloysteel

Contributingfactors

Quench cracks

Quench cracks

(1) Wrong material(2) Waterhammer

(1) Improper torque(2) Some bolts too

short

Correctiveaction

Bolts replaced

Bolts replaced

All bolts replaced with lowalloy steel (A1SI 4140) bolts

Bolts replaced

(1) Broken capscrew replaced(2) All impeller capscrews to be

replaced with stainless steelcapscrews

4 mounting bolts replaced

(1) Failed bolts and short boltsreplaced

(2) Bolts retorqued with cali-brated torque equipment

(3) Quality assurance plan forbolting improved

Page 37: 3.1/40 - International Nuclear Information System · 2004. 12. 24. · damage nuclear fuel and limits the operation of nuclear reactor. In foreign reactors operated more than 10 years,

Table 11. Failure of X-750.

Plant Date

Japanese plants: Mihama 3, Takahama 2,Ikatal.Ohi

French plants: Gravelines 1, Fessenheim 1,Bugey 2, Bugey 4, Tricastin 4

North Anna 1

Beaver Valley 1

Pt. Beach 1

Farley 1

Pt. Beach 1

Salem 1

Trojan

Surry 1

D. C. Cook 2

Pt. Beach 1

1978 and later

1982 and later

May, 1982

July, 1983

Jan., 1984

Feb., 1984

Feb., 1984

Mar., 1984

May, 1984

Oct., 1984

Jan., 1985

Apr., 1985

- 30 -

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Table 11. Continued.COMPONENT

FUEL ASSEMBLY HOLDDOWNSPRING (B&W)

CONDITION

FUEL ASSEMBLY HOLDDOWNSPRING (COMBUSTION ENGI-NEERING)

FUEL ASSEMBLY HOLDDOWNSPRING (CINLRAL ELECTRIC)

CRDM SPRINGS:BUFFERSEGMENT ARM

BELLEVILLE

HOT-ROLLED, ANNEALED AT 2100F,(1149C) COLD-DRAWN, ANNEALED AT2100F (1149C), COLD-DRAWN,COLD-COILED, AGED AT 1350F(732C) FOR 16 HOURS (AMS 5698)

SOLUTION-ANNEALED AT 2100F,(1149C) COLD-DRAWN, COILEDAND AGED (AMS 5699)

NO, 1 TEMPER OR SPRING TEMPERWIRE

NO. 1 TEMPER WIRE (AMS 5698)

COLD-ROLLED, SOLUTION-ANNEALED ATJ800F (982C), AGb.U AT 135OF (X32C)FOR 8 HOURS <• 1150F (621C) FOR ATOTAL AGING MMt OF 18 HOURS(AMS

ENVIRONMENT

COMPRESSED BETWEEN STAIN-LESS STEEL PLATES, EXPOSEDTO PWR COOLANT FLOW AT^15 fps, 600F (316C), 2200PS1, MEDIUM TO LOW NEUTRONFLUX

COMPRESSED BETWEEN STAIN-LESS STEEL PLATES, EXPOSEDTO PWR COOLANT FLOW

BWR COOLANT

NON-FLOWING PWR COOLANT400F (204C), MEDIUM TO LOWNEUTRON FLUX

REMARKS

\3500 IRRADIATED, MAXIMUMEXPOSURE 8 YEARS, 63 KSIT0RS10NAL STRESS/ 34 FATIGUE-INITIATED FAILURES, SIX DIF-FERENT PLANTS

FOUR SPRINGS PER ASSEMBLY,OVER 10,000 MADE, A FEWFAILURES IN E^RLY SEVENTIES,CAUSE UNKNOWNJ

iNO REPORTED FAILURES IN 15YEARS OF EXPERIENCE

STRESSES NORMALLYBECOME HIGH DURINGTRIP, NO REPOIIN OVER 10 YEARS

ARE LOW BUTA REACTOR

>!TED FAILURESEXPERIENCE

CONTROL COMPONENTRETAINER SPRING

CONTROL COMPONENTPillNGER

SPRING TtMPER AMS 5699B

NO, 1 TEMPER, AMS 5698C

NON-FLOWING PWR COOLANT•-600F (316C), 2200 PS I,MEDIUM TO LOW NEUTRON FLUX

NON-FLOWING PWR COOLANT AT•••600F (316C), 2200 PSI,MEDIUM TO LOW NCUTROtl FLUX

v-1000 IRRADIAMAXIMUM EXPOSl•<-5J KSI TORS I (REPORTED FAIL!

ED SINCE 1978,RE 4 YEARS,'NAL STRESS, NO•RES

^2000 IRRADIAJED *l KSITORSIONAL STRESS, NO REPORTEDFAILURES I

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CO

to

Table 11. Continued.

COMPONENT

POWER OPERATED RELIEFVALVE DISC SPRING

SECONDARY SIDE VALVESPRING

BAFFLE-TO-FORMER BOLT

REACTOR VESSEL UPPERCORE BARREL BOLT (B&W)

REACTOR VESSEL LOWERTHERMAL SHIELD BOLT(B&W)

REACTOR VESSEL UPPER COREBARREL BOLT (FOREIGN)

CONDITION

AS SUPPLIED

AS SUPPLIED

ANNEALED AT 1700F (927C),MACHINED HEAD, ROLLED THREAD,AGED AT 1345F (729C) FOR 8 HOURS+ 1150F (621C) FOR 8 HOURS

ASTM A637, GRADE 688, TYPE 2

HTH

UNAVAILABLE

FUEL ASSEMBLY BOLT(FOREIGN)

UNAVAILABLE

ENVIRONMENT

PWR PRIMARY STEAM AT(338C), ALTERNATE WETTINGAND DRYING

PWR SECONDARY SIDE COOLANTAT 300 TO 400F (149-2CMC)

PWR PRIMARY COOLANT, 650F(343C)

PWR PRIMARY COOLANT, 550 TO600F (288-316C), MODERATENEUTRON FLUX

PWR PRIMARY COOLANT, 550 TO600F (288-316C), MODERATENEUTRON FLUX

PWR COOLANT, 670F (354C)

BWR COOLANT

REMARKS

STRESS NOT DE-FAILURES, SOMREPORTED ^8 Y

STRESS NOT DEREPORTED FAILYEARS OF SERV

HIGHLY STRESS!KSI BENDING A;RATE (IGSCC)BIBLIS-TYPE RYEARS OF SERV

STRESSED 7

FAILURES INSERVICE

ERMINED, NOPITTING

ARS OF SERVICE

ERM1NED, NOIRES IN OVER 10CE

!D, 100 TO 200iOUT 10% FAILUREN SEVERAL:ACTORS (KWUJ, i\CE

OF THE MATERIALYIELD STRENGTH, NO REPORTED

YEARS OF

NO REPORTED FAILURE IN 3YEARS OF SERV

STRESS LEVELSMODERATE, NO FAILURES INENEL/TRINO (ICHOOZ (FRANCE

CE

BELIEVED TO BE

CORE BARREL BQLTS WITHYEARS SERVICE!

ALY) AND SENA/OF 160 TOTAL

12

USED SINCE 1977 IN ASEA-ATOMBWR FUEL ASSEMBLIES, FOURPER ASSEMBLY, HIGH STATICSERVICE STRESS, 7 FAILURESDUE TO IGSCC SjINCE 1982

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Table 11. Continued.

COMPONENT CONDITION

CONTROL ROD DRIVE GUIDETUBE SUPPORT PINS(FOREIGN AND DOMESTIC)

JET PUMP BEAM

VARIOUS TREATMENTS 1625 TO 2100F(885-11490 FOR 1/2 TO 2k HOURS+ 1150F (621-843C) FOR 8 TO 20HOURS

AH

ENVIRONMENT

PWR PRIMARY COOLANT, ^570TO 620F (299-327C), NEUTRONDENSITY LOW TO MODERATE

BWR COOLANT

RFMAR

100 PER PLANTiSTRESSEDSINCE 1978USA

IGSdC

HIGHLY STRESSBENDING), IG5SINCE 1979BOTH FOREIGN

HIGHLYFAILURESJAPAN, FRANCE,

ED Cv-90 KSICC FAILURES3 REACTORS,

AND DOMESTIC

i

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Table 12. Failure of A286.

COMPONENT

REACTOR VESSEL INTERNALSBOLTING (B&W)

REACTOR VESSEL EXTERNALBOLTING

GUIDE BAR BOLT COVERBEAMS

TIE ROD

FUEL ROD LOWER SPRING

CRDMMOTOR TUBE BOLTNUT CLOSURESCREWBEARING PLATE

CONDITION

CONDITION A AND B

CONDITION A AND B

SOLUTION-ANNEALED AT 1688F(920C) FOR 1 HOUR + AGED 1328F(720C) FOR 16 HOURS ( ASTMA-H53 GRADE 660, CONDITION A)

SOLUTION-ANNEALED AT 1688F(920C) FOR 1 HOUR + AGED 1328F(720C) FOR 16 HOURS ( ASTMA-453 GRADE 660, CONDITION A)

ASTM A-638, GRADE 660, TYPE 1

CONDITION A AND CONDITION B

ENVIRONMENT

PWR PRIMARY COOLANT, MODERAT-ELY HIGH NEUTRON FLUX

AIR

BWR COOLANT

BWR COOLANT

HELIUM ATMOSPHERE INSIDE OFFUEL ROD, HIGH NEUTRON FLUX,TEMPERATURE •>- 600F (316C)

NOT EXPOSED TO PWR PRIMARYCOOLANT TEMPERATURE >(2400, LOW TO MODERATENEUTRON FLUX

REMARKS

HIGH STRESS,! FAILURES 0.5 TO> 50% DEPENDING ON THE APPLI-CATION, EXTEjNSIVE USE, 10YEARS SERVICE EXPERIENCE

HIGH STRESS,] NO FAILURES IN^ 10 YEARS (JF SERVICE

IGSCC FAILURES HAVE OCCURREDIN ASEA-ATOf1982, VERY hCOVER BEAMS

PLANTS SINCEIGH STRESSES, 4AND 30% OF THE

GUIDE BAR BOLTS HAVE EXPER-IENCED CRACKING IN 4 PLANTS

LOADED TO *• |30S OF THEMATERIAL YIEJLD STRENGTH, NOFAILURES IN k 13 YEARS OFSERVICE :

LOW STRESSES (18 KSI TOR-SIONAL), 700,000 USED TODATE, NO FAILURES REPORTED

NO REPORTED JFAILURES IN 10YEARS OF SEFJV1CE, BOLTSSTRESSED TO J2/3 OF MATERIALYIELD STRENGTH, VERY LOWSTRESSES ON |NUT CLOSURE, ANDBEARING PLATiE

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Table 12. Continued.

OJCJl

COMPONENT

VENT VALVE JACK SCREW

PRIMARY COOLANT PUMPSHAFTS

CONDITION

CONDITION A

CONDITION A

PRIMARY COOLANT PUMPIMPELLER BOLTS ANDDRIVE PINS

CONDITION A

ENVIRONMENT REM/JRKS

FLOWING PWR PRIMARY COOLANT> 600F (316C), LOW TO MOD-ERATE NEUTRON FLUX

PWR WATER AT VARIOUS TEMPERA-TURES, NO NEUTRON FLUX

NON-FLOWING PWR WATER AT-*• 550°F (290*C), NO NEUTRONFLUX

STRESSES COMPRESSIVE NOREPORTED FAILURES IN OVER10 YEARS OFJSERVI.CE

|LOW BENDING [AND TORSIONALSTRESSES, liFAILURE, 3SHAFTS CRACKED AT ONE PLANT,HIGH CYCLE fjATIGUE

LOW STRESSES', SEVERAL BOLTSAND PINS CRACKED OR FAILED,INVESTIGATION ONGOING

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:§TO

100

90

80

70

60

50

40

30

20

10

0

Bolted Joints Containing No Failures (24 Joints)Bolted Joints Containing Failures (13 Joints)

%Failure=Wof Bolts with U/T Indications

#of Bolts per Joint U/T Inspected

(Failure Threshold Region)

xlOO'

A

0 20 40 60 80 100 120 1400 (140) (280) (420) (560) (690) (840) (980)

160 180 200(1120) (1260) (1400)

Bolt Fillet Peak Stress (Nominal Stress x KT), KSl(MPa)

Fig. 6. Incidents of bolt failures

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1 H 316

1.2.

3.

8, 9, 10

H ^ 11.

*\\ 2 m X-750

1. 7]2:-i-^ : n ^ 12

2. 71 Til3 ^ : =L% 13, 14

3 m A286

1.2.

15

, 17

- 37 -

Page 45: 3.1/40 - International Nuclear Information System · 2004. 12. 24. · damage nuclear fuel and limits the operation of nuclear reactor. In foreign reactors operated more than 10 years,

YOUNG'S MODULUS, 1O6 psi

SPECIFIC HEAT, tO'z Biu/IIWCF)

SPECIFIC HEAT, 10z J/(kg)(*K)

2 ) CD

58

T 1

yy

yy

i

E >I i3 u>

i i i

y,Ay

1 i i i

-

-

-

-

-

YOUNG'S MODULUS, 104 MPo

THERMAL EXPANSION, 10 in./(in.)('F)Co

b bpb

8

\

1 1

k\ s

\

1

\

1

—1•*<

•oit

. '*. 6

>. V . \\ \ \

Scost

Typ

e 310

Is

---

THERMAL EXPANSION, 10"6 cm /(cm)CK)

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200

Temperature (° F }

600 1000 1400

Expected :2 see lor reannealedmater i Ol. ptate/pipe products(ORNLdata on 20 heals )

—•-Expected 12 see lor mill-annealed: 'inn maierial.tube /pipe/plate• ^ r products {U.S,Japanese.and

UK dota.)

Nudear sysiems materials

B

400

3S0

I 300

Temperature | ' F !

200 600 1000 1400

40 i

- — Expected ; 2 see lor mtll-onneoled materialTube pipe plate products (US.*Japanese, and U K data )

Nuclear systems mcrterialshandbook minimum.

oa.

JZ

sire

nle

n

E

5

/uu

600

5 0 0

400

300

2 0 0

100

0

/ ^ ^ ^ ^ ^/ ^

/Nuclear systemsmote riots handbookminimum.

(b)

i \ -

V

0

100

90

80

70

60

50

40

30

20

10

0

uu

90

B0

70

6 0

SO

3 0

2 0

10

Elongalgauge

- \

" \ ^ \

ion in 254 and 50.8mmlength

^ > / - ' •

^ ^ ^

tc) , , i

100 400 600Temperature (CC}

100

90

80

70

60

Elongation in 25.£ and SO.6mmgouge length.

?00 £00 600 BOOTemperature ( c C)

Fig. 8. Tensile properties of austenitic stainless steel.

- 39 -

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10" '

MPa20

VTri40 60 60 100

10-

O | Z

o

Ocn

jc

O

o

10"

Type 316stainless steelsolution,annealed

Unaged

Aged5000hr.at593°C

°« Zero hold- timeA* 6 Sec holdo» 60 Sec hold

10"

10"

MPa VrrT20 40 60 80 100

10"

u

10'o

10"

10"

1 1 1 1Type 316 stainlesssteel 20'/.work.

Unaged60 sechold

/

60 sec/"hold / y

wJP

Zero yS

cold

/Aged/5000hr.

/at 593°C

/ /

//Unaged/ zero

hold-time

- 10o

E

10"

10 20 40 SO ftO 100

Stress intensity factor range,(AK) , ksi T

10 20 40 60 60 100

Stress intensity factor range(AK), ksi

10E-5

1a•C5

10E-7

10E-7

2o 10E-8

10E-9

" R = 0.7

= 0.2

0SKhl8N10TJ I I t

10E-9

Unalloyed carbon steel (•, R=0.2),Buttering weld metal of EA-395/9 (X, R=0.1)Stainless steel weld EA-400/10U (A) at 350°CButtering high nickel weld metal of EA-395/9 (O,R=0.2) at270°C in water.

10010 20 40

AKMpa.ml/2

Curves 1 & 2: in airCurves 3 & 4: in reactor water(T = 300°C; 1 % H3BO3; pH = 8; O, =O.lmg/kg). Loading factor R = 0.2 &0.7.Points depict data of autoclave tests

Fig. 9. Fatigue properties of austenitic stainless steel.

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CREEP RATE, %/h0.00001 0.0001

Rupture time— - Creep rate

CREEP RATE, %/h0.00001 0.0001

(000 10,000RUPTURE TIME, h

- " —

^ ^ \

-' Ruptureo Creep r(

1200°F(648|

°C)

1350oF(734°C)-

1500°F(815°C)I" i i i i i "18OO°F(981°C).timt e .

1I1

500°

Rnn°o

F~

F

lype 3 l t

689.5

275.8

69

27.6

6.9

2.8

689.5

275.8

Rupture tfmeCreep rate

1 1

~—nn f

rCreep rate

r III

r—

—^

-»•

• ^

• ™

• * •

* -

^ —<

, — •

1"ype 321"

ll

689.5

275.8

69

27.6

6.9

2.8

100 1000 10,000 100,000RUPTURE TIME.h

Fig. 10. Creep properties of austenitic stainless steel.

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H«l «n« W«M« at 15CC

'• y

OUT WO (LTy

*^ Unitt

• UN. fTl) t>w

« UK fTU tto>• El fTU WW• I t HU Uw

• J I K tn-i n* IC CTIJ fcr

« t i fTU kr

* a»O [T(.| in

* <w ^Tl *»

Fig. 11. Effect of irradiation on mechanical properties of austenitic stainless

steel.

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100 -

60 •

8 6°8CO

o

DO

32

0.0?

Tro« 3CXSS

oo

0?C.iC«

ooa

0o

20

0

O.Zwxn

ft nu

Neutton Fluence (n/m1, E> 1 MeV)

CPXM-A.MJ1 __,_ CP304-B, fto Kudy# HP3O4-A. W« M J *H A HP>M-CO(VJ,T),*l.»A<y ^p

ca

10"10E20 10E21

Nwtroci Flu*nc» (R/cmE2, E>1

100

80

8 «»en

20

Tp«« 3CMSS«

a

oA

ooo

Qo «

a

io» ~io»~ io" io"Neutron Ftuence (nAn2. E>1MeV)

Fig. 11. Continued.

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1200

I 000

toe •

-i*

11*

s .,

^-

r7%C0LD Y.ORKEDS a U T K N TREATH)

_J 1 I L.

0 10 20 30 W 50ATOM DISPLACEMENTS N/2

800

700

. M O

O 400

UJ

fe300

200

1000.1

ULTIMATE ^ i i

. 1 — • * 1

YIELD y ^ 5 r

*7/ o_/ or *

ooT

LKUV

f j lU lu>utm*.•»

t

304SS

• *» •

»4«lr'M««r'

u.ir'

Ti.*C

«s3B .Vtmmm

1 10EXPOSURE, dpa

100

800

700

£ 400

B»200

100

ULTIMATE

YIELD J

J/J o

_/? °r \

0

r

"-/„,u tinut j iILT7

Y

si ess

| 4 l H-7

U ft W*7

•c

c*m .m

S I

0.1 1 10EXPOSURE, dpa

100

Uniform elongationc) 304&316 S.S.

Fig. 11. Continued.

44 -

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Table 13. Physical properties of X-750.

Mean Linear Expansion,

Tempera-ture, °F

from 70°F toTemperature Shown

ThermalConductivity,Btu/inVhr/

sq ft/°F

i

Specific HeatBtu/lb/°F

Diffusivity,sq ft/hr

ElectricalResistivity,

j ohm/circi mil/ft

- 2 5 0-20O- 1 0 0

70200400600800

10001200140016001800

6.56.66.7

7.07.Z7.57.88.18.48.39.39.8

677074838998

109120131143154164

0.0730.0800.0900.1030.1090.1160.1200.1250.1300.1370.1510.171

0.1500.1430.1350.1320.1330.1400.1480.1580.1690.1730.1720.164

I

731739746761771783786775761

• Material hejt-lreat«l 2100f 12 t*. A.C, + IS50Tl» hr. A.C + l300f/M hr. A.C.

Tempera-ture, °F

801

500100012001350150016001800

Static

31.028.725.023.021.018.5

-

Modulus of Elasticity, 10'

Tensioni

j!jij

i

Dynamic

31.029.126.725.524.423.222.120.0

psi

Torsion

Static

U.O10.29.08.1_

-

1 Poissofl's ratio —0.29.

Density, gm/cc j 8.25Ib/cu in. j 0.298

Melting Range, °F j 2540-2600Curie Temperature, °F {

As Hot-Rolled - 225Triple-Heat-Treated <21OO*F/2 hr, AX., + 150017 ';24 hr. A.C., +1300°F/20 hr, A.C.) ; - 193

Magnetic Permeability (70°F, 200 H)As Hot-Rolled ; 1.OO20Triple-Heat-Treated (210O°F/2 hr. A.C. + 1500°F/ '•24hr.A.C., + 130Cr>F/20hf,A.C.) j 1.0035

Emissivity (Oxidized Surface) '6O0°F j 0.895

2000°F ! 0.925

Linear Contraction during Precipitation Treatment i(1300*F/20hf),in./in. !

Hot-Rolled | 0.OOO4420% Cold-Rolled | 0.00052Annealed i 0.00026

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Table 14. Tensile properties of X-750.

Heat ; j Tensile ivield Strength iEionga-Treat- jOiameter, Strengtfi.J(0.2%Offset), i tion,merit ' in. lOOOpsij 1000 psi ; %

Reductionof Area,

jHardness,: Rockwelli C

AB

AB

A6

AB

AB

AB

AB

AB

AB

AB

AB

AB

AB

A8

"fa

%

%

| 1

i 1 V , 4

| l¥i«

1%

Wi

: iv%

: ivi

; 2V«

i; 2 V?

: 215/l6

i

1

11

I

i

j

199.0 I196.0 |

194.0 ;192.5 j

193.5 ;

191.0

194.5 |197.0 |

187.5 i190.0 '•

189.5 :192.5 i

195.0 i195.5 i

190.5 I190.5 i

188.0 ;189.0 j

198.0 1196.5 |

190.5 :

190.5 :

189.5 ;189.5

184.0 :184.5

180.5 '184.0 !

146.0149.0

139.0139.0

137.5140.0

140.0146.0

130.5139.0

134.5137.5

132.5138.5

136.0136.5

132.8132.0

141.0142.0

129.5131.0

136.5140.5

135.0137.5

128.5137.0

i 25.0! 24.0; 27.0

25.0

25.0• 22.0

• 24.D

i 21.0

I 25.0i 22.0

• 24.0

; 23.0

• 25.0: 26.0

24.0; 23.0

! 27.0• 26.0

! 24.0i 25.0

' 26.0; 25.0

; 22.0; 2i.o

23.0, 22.0

! 24.0I 23.0

41.542.3

46.447.7

38.538.8

40.242.8

41.835.4

39.541.0

43.243.5

43.Q43.0

46.045.0

42.046.3

43.040.5

30.521.5

38.036.0

35.038.0

36.038.0

38.039.0

38.039.0

40.040.0

33.039.4

39.040.0

35.042.0

38.037.0

34.040.0

41.040.0

40.041.0

39.039.0

38.039.0

34.038.0

46 -

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-V

1

1

M Smooth Specimen

1

* —

Notched So*

i

i i

i i

i10* 10'

Cycles toFjiluie

00

so

in

rlOOOf

** UlATt

__«——

^ ^

1 . . . ._

" '

i?oof "*"

Fig. 12. Fatigue and creep properties of X-750.

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10 20

MPa Jm

30 40 50 60 70

r rCondition

m 3A 4T 12a 14

100

JC

£

10

#3(X-750. AH)'»(A-286)

#12(718) ~(X-750 -#1 Temper)

!

10

.1

.01

10 20 30 40 50Stress Intensity, tai /1HT

60 70

Fig. 13. Corrosion properties of X-750.

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a:X

u

Fe-2SNi-15Cr-2Ti-1.5Mn-l. 3Mo-0.3V

(8)

THERMALCONDUCTIVITY

800 1200 1600

T E M P - F»

WD,

a iowa,2

2 9

Fe-Z5Ni-15Cr-2Ti-l.5Mn-l.JMo-,0.3V

MEANCOEF UNEARTHERMAL EXPANSION

= (8)

—m-—(34)

-XFROM RT TOTEMP INDICATED

400 800 1200 1600TEMP - F • :

1 40

36

Fc-25Ni0.3V

/

15Cr-2T

/

ELJECTK

- l .5Mn-

CALBESL

.3Mo-

STIVITY

0 400 800 1200 1600TEMP - F

Fig. 14. Physical properties of A286.

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zoo

400 qpO 1200 1600 2000TEMP - F

Fe-25Ni-15Cr-2Ti-1.5Mn-1.3Mo-0.3V 7/8 IN1800F. 1HR, OQ+1325F, 16

TIECHA RPY V

BARHR

2'-400 0 400 800 1200 1600

TEMP - F

Fig. 15. Tensile and impact properties of A286.

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Fe-25Ni-lSCr-2Ti-l.SMn-l.3Mo-C.3V80j— BAR STOCK

16S0F. 2HRS. OQ • IJZSF. 16 HRS AC

SO

MEAN STRESS - F - KSIMF

200

100"

700FJ") F « - Z S N i - 1 5 C r - 2 T i - l - 5 M n - 1 . 3 M o - 0 . 3 V

BARQ. 1800F, 1 HR, OQ _

). t 1325F. 16 HR

100 1000 10TIME - HR

,000

Fig. 16. Fatigue and creep properties of A286.

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10 J I I I

1200

9 1

<u

oi

o

oa>enca!_C1J<

0.1Material Ht.

V 7 1 8 'T 718, #1 and Special

(B A-286, #1a A-286, Special

A 316

0.01 n t,t10 20 30 .40 50 60 70

Stress Intensity K, (MPa <Jm)

Fig. 16. Continued.

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A S M E Specification

1. 316 ^31^131^ ^ (SA-479)

2. A286 (SA-453, Grade 660)

3. X-750 (SB-637 UNS N07750 : Grade 688 )

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SPECIFICATION FOR STAINLESS ANDHEAT-RESISTING STEEL BARS AND SHAPES FOR

USE IN BOILERS AND OTHER PRESSURE VESSELS

SA-479/SA-479M

(Identical with ASTM Specification A 479/A 479M-90 except for editorial differences in 3.1.8, 5.1.4, 5.2, and Table 2)

1. Scope

1.1 This specification covers hot- and cold-finishedbars of stainless and heat-resisting steel, includingrounds, squares, and hexagons, and hot-rolled or ex-truded shapes such as angles, tees, and channels for usein boiler and pressure vessel construction.

1.2 The values states in either inch-pound units orSI (metric) units are to be regarded separately as stan-dards; within the text and tables, the SI units are shownin [brackets]. The values stated in each system are notexact equivalents; therefore, each system must be usedindependent of the other. Combining values from thetwo systems may result in nonconformance with thespecification.

1.3 Unless the order specifies- the applicable "M"specification designation, the material shall be fur-nished to the inch-pound units.

2. Referenced Documents

2.1 ASTM Standards:A 262 Practices for Detecting Susceptibility to Inter-

granular Attack in Austenitic Stainless SteelsA 370 Test Methods and Definitions for Mechanical

Testing of Steel ProductsA 484/A 484M Specification for General Require-

ments for Stainless and Heat-Resisting Bars, Billetsand Forgings

A 751 Methods, Practices, and Definitions for Chemi-cal Analysis of Steel Products

E 112 Methods of Determining the Average Grain Size

E 527 Practice for Numbering Metals and Alloys(UNS)

2.2 Other Document-SAE JIO86 Recommended Practice for Numbering

Metals and Alloys

3. Ordering Information

3.1 Orders for material under this specification shallinclude the following:

3.1.1 Quantity (weight or number of pieces),

3.1.2 Name of material (stainless steel),

3.1.3 Condition (annealed, or others included inSection 5,

3.1.4 Finish (see Materials and Manufacture sec-tion of Specification A 484/A 484M),

3.1.5 Applicable dimensions including cross sec-tion and length,

3.1.6 Shape (rounds, hexagons, etc.),

3.1.7 Type or UNS designation, and

3.1.8 Specification designation and year of issue,

NOTE 1—A typical ordering description is as follows: 50001b stain-less steel, annealed and centcrless ground, round bar I in. [25 mm]in diameter, 10 to 12 ft [3 m to + m] Type 304, ASTM SpecifiactionA 479-XX plus any supplementary or optional requirements.

3.2 Orders for material under this specificationshould consider including the following:

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SA-479/SA-479M 1992 SECTION II

3.2.1 Supplementary Requirements invoked forspecific services (described at the end of this standard):51 Materials for High Temperature Service52 Corrosion Test53 Product Analysis54 Material for High Cycle Fatigue Service55 Material for Optimum Resistance to Stress Corro-

sion Cracking

3.2.2 Whether bars are to be rolled as bars or cutfrom strip or plate,

3.2.3 Preparation for delivery (see Preparation forDelivery section of Specification A 484/A 484M),

3.2.4 Marking requirements (see Marking sectionof Specification A 484/A 484M).

4. General Requirements

4.1 In addition to the requirements of this specifica-tion, all requirements of the current editions of Specifi-cation A 484/A 484M shall apply.

5. Heat Treatment

5.1 Austenitic Grades:

5.1.1 Except for the.strain-hardened type (see5.1.3), and the hot-rolled grade (see 5.1.4), all austeniticgrades of stainless steels shall be furnished in the solu-tion annealed condition, with subsequent light colddrawing and straightening permitted (see Supplementa-ry Requirement S5 if annealing must be the final opera-tion). Solution annealing for all grades except H grades(see 5.1.2) and S31254 (see 5.1.5) shall consist of (/)heating the material to a temperature of 1900°F[1040°C] minimum so that grain boundary carbidesenter into solution, and cooling rapidly to prevent grainboundary carbide precipitation; or alternatively (2) (ex-cept for the columbium and titanium stabilized grades309Cb, 310Cb, 316Cb, 316Ti, 321, 347, and 348) imme-diately following hot working while the temperature isabove 175O°F [955°C] so that grain boundary carbidesare in solution, cooling rapidly to prevent grain bound-ary carbide precipitation. When Supplementary Re-quirement S2 is invoke, all austenitic grades exceptS3O815 shall pass the intergranular corrosion test re-quirement described in S2.

5.1.2 For H grades, the minimum solution anneal-ing temperatures shall be as follows:

5.1.2.1 When hot finished, 1900°F [1040°C] for

Types 304H, 3O9H, 310H, and 316H; 1925"F [1050°C]for Types 321H, 347H, and 348H,

5.1.2.2 When cold worked prior to solution an-nealing, 1900°F [1040"C] for Types 3O4H, 309H, 310H,and 316H; 2000T [1090°C] for Types 321H, and 348H.

NOTE 2—Solution annealing temperatures above 195OT {1O65°C]may impair the resistance to intergranular corrosion after subsequentexposure to sensitizing conditions in the stabilized grades, Types 321,321 H. 347 H, 348 and 348 H. When intergranular corrosion is ofconcern, the purchaser should specify the corrosion test of S2 (tobe conducted on sensitized specimens). The manufacturer may, ifnecessary, use a lower temperature resolution anneal or a stabiliza-tion anneal after a high temperature solution anneal in order to meetcorrosion test requirements. Consideration should be given to thecorrosive media before using a stabilization anneal at less than !80O°F[98CTC]. as such a treatment may not be fully effective for all media.

NOTE 3—Grain size requirements for the H grades are described inSection 7.

5.1.3 Strain Hardened Austenitic Type 316 —When Type 316 is desired with increased mechanicalproperties, the strain hardened condition may be spec-ified and is produced by solution annealing, as de-scribed in 5.1.1, followed by strain hardening sufficientto meet the required mechanical properties. Solutionannealed and strain hardened material shall be capableof meeting the intergranular corrosion test of Supple-mentary Requirement S2.

5.1.3.1 Two strain hardened conditions havebeen established for different applications: Level 1 andLevel 2 (see the Mechanical Property Requirementstable).

5.1.4 High tensile Type XM-19 shall be in thehot-rolled or strain-hardened condition and shall becapable of meeting the mechanical property require-ments of the Mechanical Property Requirements Table2 and passing the mtergranular corrosion test pre-scribed in S2. The strain hardened condition is achievedby solution annealing followed by cold working suffi-cient to develop the required mechanical properties.

5.1.5 Solution annealing of S31254 shall consist ofheating the material to a temperature of 2100°F[1I5O°C] minimum, for an appropriate tune followedby water quenching or rapidly cooling by other means.

5.2 Austenitic-Ferritic Grades — S3255O shall be fur-nished in the annealed condition with subsequentstraightening permitted. The annealing treatment ofS3255O shall consist of heating the material to a temper-ature of 1900"F [1038°C] minimum for an appropriatetime followed by water quenching or rapid cooling byother means. The annealing treatment of S32950 shallconsist of heating the material to a temperature of1825T [995"C] to 1875°F [1025°C] for an appropriate

A93

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PART A — FERROUS MATERIAL SPECIFICATIONS SA-479/SA-479M

time followed by water quenching or rapid cooling byother means.

5.3 Ferritic Grades — Ferritic grades shall be an-nealed to meet the requirements of the MechanicalProperty Requirements table.

5.4 Martensitic Grades:

5.4.1 All grades of martensitic steels shall be sup-plied in either the annealed condition or in the tem-pered condition as specified by the purchaser (see3.1.3). Tempered material shall be normalized, or shallbe liquid quenched from 1700T [925eC], minimum,followed by tempering in accordance with 5.4.2, 5.4.3,or 5.4.4.

5.4.2 Types 403 and 410 tempered material shallbe held at tempering temperature for at least 1 h/in.(25.4 mm) of cross section as follows:

5.4.2.1 Condition 1 — 1250T [675°C] mini-mum, 1400T [760°C] maximum.

5.4.2.2 Condition 2 — 1100°F [590°C] mini-mum, 1400T [760°C] maximum.

5.4.2.3 Condition 3 — 1050T [570°C] mini-mum, 1400T [760°C] maximum.

5.4.3 Types XM-30, and 414, and 431 temperedmaterials shall be held at 1100T [59CTC], minimum,for at least 1 h/in. [25 mm] of cross section. Maximumtempering temperature shall be 1400T [76O°CJ.

5.4.4 For S41500 heat to 1750T [955°C] mini-mum, air cool to 200°F [95°C] or lower prior to anyoptional intermediate temper and prior to the final tem-per. The final temper shall be between 1050°F [565°C]and 115O°F [620°C].

5.4.5 When the purchaser elects to perform thehardening and tempering heat treatment, martensiticmaterials shall be supplied by the manufacturer in theannealed condition (see 5.4.1). In this case it shall bethe purchaser's responsibility to apply the proper heattreatment and to conduct the tests he deems necessaryto assure that the required properties are obtained.

6. Chemical Composition

6.1 Chemical composition shall be reported to thepurchaser, or his representative, and shall conform tothe requirements specified in Table 1.

6.2 When a product analysis is performed in accord-ance with the general requirements specifications, thechemical composition thus determined shall conform

to the expanded tolerances for product analysis shownin the general requirements specifications unless Sup-plementary Requirement S3 is invoked.

6.3 Methods and practices relating to chemical anal-ysis required by this specification shall be in accordancewith Methods, Practices and Definitions A 751.

7. Grain Size for Austenitic Grades

7.1 All austenitic grades shall be tested for averagegrain size by Methods E 112.

7.2 The H grades shall conform to an average grainsize as follows:

7.2.1 ASTM No. 6 or coarser for Types 304H,309H, 310H, and 316H,

7.2.2 ASTM No. 7 or coarser for Types 321H,347H. and 348H.

7.3 For S32615, the grain size as determined in ac-cordance with Methods E 112, comparison method,Plate 11, shall be No. 3 or finer.

8. Mechanical Property Requirements

8.1 The material shall conform to the mechanicalproperty requirements specified in Table 2 for thegrades ordered. At least one room-temperature testshall be performed by the manufacturer on a samplefrom at least one bar or shape from each lot of material.

8.2 The yield strength shall be determined by theoffset (0.2%) method as prescribed in Test Methodsand Definitions A 370.

8.3 Martensitic material supplied in the annealedcondition shall be capable of meeting the hardened andtempered mechanical properties when heat treated inaccordance with the requirements of 5.4. Hardnessmeasurements shall be made at a location midway be-tween the surface and the center of the cross section.

8.4 The martensitic grades shall be capable of meet-ing the minimum hardness requirements after heattreating as specified in Table 3.

9. Corrosion Testing

9.1 Austenitic stainless steels soluttion annealed bythe alternative method (see (2) in 5.1.1) shall be testedand pass the intergranular corrosion test requirementsdescribed in S2.

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SA-479/SA-479M

10. Certification

1992 SECTION tl

10.1 The material manufacturer's certificate of com-pliance certifying that the material was manufacturedand tested in accordance with this specification, togeth-er with a report of the results required by this specifica-tion and the purchase order shall be furnished at thetime of shipment. The certification shall be positivelyrelatable to the lot of material represented.

11. Product Marking

11.1 In addition to the marking requirements ofSpecifications A 484/A 484M, materials which havebeen heat treated in accordance with 5.1, 5.2, or 5.3,5.4 or have been strain-hardened in accordance with5.1.3 shall be identified by placement of the followingsymbols after the grade designation:

11.1.1 Austenitic Grades:

11.1.1.1 All grades in the annealed condition—A.

11.1.1.2 Strain hardened Type 316, Level 1 — SI,

1L1.L3 Strain hardened Type 316, Level 2 — S2,

11.1.1.4 Hot-rolled Type XM-19 — H,

11.1.1.5 Strain hardened Type XM-19 — S,

11.1.1.6 Material meeting Supplementary Re-quirement SI — ELT (unnecessary for H grades).

11.1.2 Austenitic-Ferrilic Grades— All grades inthe annealed condition—A.

11.1.3 Ferritic Grades — All grades in the an-nealed condition—A.

11.1.4 Martensitic Grades:

11.1.4.1 All grades in the annealed condition—A

11.1.4.2 Types 403 and 410—COND 1, COND2, or COND 3 as appropriate for the tempering temper-ature employed.

11.1.4.3 Type 414, S41500, and Type XM-30tempered materials—T.

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PART A — FERROUS MATERIAL SPECIFICATIONS

TABLE 1CHEMICAL REQUIREMENTS

SA-479/SA-479M

UNSDesigna-

tion*Type

Composition. X

Cartxxvmax

Man-ures**.

Ptros-pho-rus.max

Euerur.max

S*con.max

Chforoium Nickel Nitrogen,max"

Molyb-denum Other Elements"

Austenrtic Gr&Oas

S20161S20910

S21600S216O3S218OOS21904S240O0S30200S30400S3 0403S30409S3WS1S30453S30600S30815S30906S3O9O9S30940

S30880S31008S310O9S31040

"112541600

S316O3S31609S31635

S31640

S31651S31653S31725S31726S321OO

S32109

S32615S34700534709

S3480O

S34809

XM-19

XM-17XM-16

XM-11XK4-29302304304L304 H304N304 LN

309S309H3O9Cb

ER308 c

310S310H310Cb

316316L316H316TI

316Cb

316N316LN

321

321H

347347H

348

348H

0.150.06

0.080.030.100.040.080.150.08C

0.0300.04-0.100.080.0300.016 max0.100.080.04-0.100.08

0.080.080.04-0.100.08

0.0200.08c

0.0300.04-0.100.08

0.08

0.080.0300.030.030.08 c

0.04-0.10

0.070.08°0.04-0.10

0.08 c

0.04-0.10

4.00-6.004.00-6.00

7.50-9.007.50-9.007.00-9.008.00-10.0011.60-14.502.002.002.002.002.002.002.000.802.002.002.00

1.00-2.502.002.002.00

1.002.002.002.002.00

2.00

2.002.002.002.002.00

2.00

2.002.002.00

2.00

2 0 0

0.0400.040

0.0450.0450.0600.06000600.0450.0450.0450.0400.0450.0450.0200.0400.0450.0450.045

0.0300.0450.0450.O45

0.0300.0450.0450.0400.045

0.045

0.0450.0450.0450.0450.045

0.040

0.0450.0450.040

0.045

0.040

0.0400.030

0.0300.0300.030

o.ox0.0300.03000300.0300.0300.0300.0300.0200.0300.0300.0300.030

0.0300.0300.0300.030

00100.0300.0300.0300.030

0.030

0.0300.0300.0300.0300.030

0.030

0.0300.0300.030

0.030

0.030

300-4.001.00

1.001,003.50-».5O1.001.00t.001.001.001.001.001.003.7-4.31.4O-2.0O1.001.001.00

0.25-0.601.501.501.50

0.801.001.001.001.00

1.00

1.001.001.001.001.00

1.00

4.80-6.001.001.00

1.00

1.00

15 00-18.0020.50-23.50

17.50-22.0017.50-22.0016.00-18.0019.00-21.5017.00-18.0017.00-19.0018.00-20.001S.0O-20.O016.00-20.0018.00-20.0018.00-20.0017.0-16.5

20.00-22.0022.00-24.0022.00-24.0022.00-24.00

19.50-22.0024.00-26.0024.00-26.0024.00-26.00

19.50-20.5016.00-18.0016.00-18.0016.00-18.0016.00-18.00

16.00-16.00

16.00-16.0016.00-18.0018.00-20.0017.00-20.0017.00-19.00

17.00-19.00

16.50-19.5017.OO-19.OC17.00-19.00

17.00-19.00

17.00-19.00

4.00-6.0011.50-13.50

5.00-7.005.00-7.008.00-9.005.50-7.502.25-3.75B.00-10.00B.OO-10.5O8.00-12.008.00-10.508.00-12.008.00-12.0014.0-15.5

10.00-12.0012.00-15.0012.00-15.0012.00-16.00

9.00-11.0019.00-22.0019.00-22.0019.00-22.00

17.50-18.5010.00-14.0010.00-14.0010.00-14.0010.00-14.00

10.00-14.00

10.00-14.0010.00-14.0013.50-17.5013.50-17.509.00-12.00

9.00-12.00

19.00-22.009.00-13.009.00-1300

9.00-13.00

9.00-13.00

0.08 -0.200.20-0.40

0.25-0.5O0.25-0.500.08-0.180.15-0.400.20-0.400.100.100.10

0.10-0.160.10-0.16

0.14.-0.20

0.10

0.10

0.18-0.220.100.10

0.10

0.10

0.10-0.160.10-0.160.100.10-0.20

1.50-3.00

2.00-3.002.00-3.00

0.20

6.O0-6.502.00-3.002.O0-3.O02.00-3.002.00-3.00

2.00-3.00

2.00-3.002.00-3.004.0-5.04.0-5.0

0.30-1.50

Cb O.10-0.30:V 0.10-0.30

Ce0.03-O.08

<Cb+ Ta) 10 x Cmin: 1.10 max

(Cb+ Ta) 10 x Cmm; 1.10 max

Cu 0.50-1.00

Ti 5 x (C + N) min;0.70 max

(Cb + Ta) 10 x Cmm; 1.10 max

Cu 0.75 maxCuO.75 maxTi 5 x (C+N) min to

0.70 max*Ti 4 x (C+NJ min to

070 maxe

Cu 1.50-2.50(Cb + Ta] 10 x C. tninCb 8 x C. min to 1.00

max(Cb+ Ta) 10 x C. min;

Ta 0.01 max; Co0.20 max

Cb 8 x C. min to 1.00max; Co 0.20 max

Austenitic-Femtic Grades

S325SOS32950

0.040.03

1.502.00

0.0400.035

0.030 1.00.010

24.0-27.026.00-29.00

4.50-6.503.50-5.20

0.10-0.250.15-0.35

29-3.91 00-2.50

Cu 1.50-2.50

Ferritic Grades

S40500S43000S43035

S44400

.-4627

S44700

S44800

405430439

XM-27

0.080.120.07

0.025

0.010'

0.010

0.010

1.001.001.00

1.00

0.40

0.30

0.30

0.0400.0400.040

0.040

0.02

0.025

0.025

0.0300.0300.030

0.030

0.02

0.020

0.020

1.001.001.00

1.00

0.40

0.20

0.20

11.50-14.5016.00-18.0017.00-19.00

17.5-19.5

25.00-27.50

28.00-30.00

28 00-30.00

0.60 max

0.50 max

1.00 max

0.50 max

0.15 max

2.00-2.50

0.04

0.035

0.015 max'

0.020

0.020

1.75-2.50

0.75-1.50

3.50-4.20

3.50-4.20

Al 0.10-0.30

Ti min = 0.20 + 4 (C+ N)

(Ti + Cb) 0.20 + 4 (C

N) min to 0.80 maxCu 0.20 max;

Cb 0.05-0.20(C •+ N) 0.025 max;

Cu 0.15 max(C + N| 0.025 max;

Cu 0.15 max

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SA-479/SA-479M 1992 SECTION II

UNSDesigna-

tion "*Type

TABLE 1 (CONT'D)Composition. %

Carbon."max

Man-ganese,

max

Phos-pho-rus,max

Sulfur,max

Silicon,max Cnromium Nickel

Nilrogen,max"

Molyb-denum Other Elements6

Martensitic G'ades

S4O300S41000S41040S41400S41500S43100

403410XM-30414c

431

0.150150.180.150 05U.20

1.001.001.001.000.5-1.01.00

0.0400 04000400.0400.0300.040

0.0300.0300.0300.0300.0300.030

0.501.001.001.000.601.00

1- 50-13.001- 50-13.501" 50-13.50r. 50-13.501i 50-14 015 00-17.00

1.25-2.503.5-5.51.25-2.50

0.5-1.0

Cb 0.05-0.30

A New designations established in accordance with Practice E 527 and SAE JiO6c polished jointly by ASTM and SAE. See ASTM DS-56C.10

B Except as required for specific aitoy type, molybdenum, litanium. nickel, cobalt. t£":a>um. nitrogen, and copper need no! be reported but shall not be present in otthan residual amounts: trie intent being to prohibit substitution of one alloy type for archer cJue to absence of control of the above named elements m certain alloys.

c See Supplementary Requirement Si .° American Welding Society designatione Nitrogen content is lo be reported.f Product analysis tolerance over the maximum limit lor cannon and mfogen to be C 002 *.G Wrought version of CA6NM.w MaKtmum unless otherwise ind*ca^ed

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PART A — FERROUS MATERIAL SPECIFICATIONS SA-479/SA-479M

TABLE 2MECHANICAL PROPERTY REQUIREMENTS A92

UNSDesignation

S32S5OS32950

S40500S43000,

S43035S44627S44400S44700S44800

S4030O,S410O0

S41400S41S00

S4310O

S41040

Type

XM-11XM-17, XM-18S20161S21800S30600S30815S31254S31725S31726S32615XM-19XM-19:

Up to 2 in. (50.8 mm), incfOver 2 to 3 in. (50.8 to 7b.2 mm), inclOver 3 to 8 in. (76.2 to 203.2 mm), :ncl

XM-19:Up to l ' / j in. (38.1 mm), inclOver I 1 / , to 2 'A in. (38.1 to 57.2 mm),

inclXM-29302, 304, 304H, 304LN, ER3O6£, 309S,

309K, 309Cb, 310S, 310H, 310Cb, 316,316K, 316TI, 31bCb, 316LN, 321, 321H,347, 347H, 348, 348H

304L, 316L304N, 316N316

3162 in. and underOver 2 to 2Vi '«• (S0.B to 63.5 rnmi, incl.

Over 21 / , to 3 in. (63.5 to 76.2 mini, incl.

-

405430, 439

XM-27

403, 410

403, 410403, 410403, 410414

4 3 1 "

XM-30XM-30

Condition

TensileStrength, min,

ksi tMPa]

Austenilic Grades

annealedannealedannealedannealedannealedannealedannealedannealedannealedannealedannealedhot-rolled

strain-hardened

annealedannealed

annealedannealedstrain-hardened

level 1strain-hardened

level 2strain-hardened

level 2strain-hardened

level 2

90[620]90 (620)

J25[860395 £655378[540)87[600)95[655]75[515)80[550]80[550]

1O0[6903

135C93O3115[7953100[6903

145U000)120[8253

1O0[690]75£515JC

70[485380[550385 (5853

95[6553

90[6203

80[5503

YieldStrength/min, ksi(MPa3

50 £345350 (345350(345350 C345335[240345(310)44(305)30(205335(240332(220355(3803

105£725)75£515)60 (4153

125 £8603105 £7253

55 £380330 £2053

25 £170)35(240)65 £45D)C

75(5153

65(4503

55 £380)

Austenitic-Ferritic Grades

annealedannealed

Ferrilic

annealedannealed

annealedannealedannealedannealed

110[7603100[690]

Grades

60 [415370 [485]

65 [450]60[415]70C465)70 [485]

Martensitic Grades

annealed

123temperednormalized and

temperedannealedtemperedannealedquenched and

tempered

70[485]

70(485]110[760]130(900]115(795)115(795)

115(795370(4853

12518603

80 £550)70 £485)

25(170)40(275)

40(275)45(310)55(380]5513803

40(275)

40(275185(5851

100(690390(620390[6203

90 [620340£2753

100 £6903

Elongation in2 in. or 50

mm, min, %

4540403540403540402535

202530

1215

3030

303D..-30

25

30

30

1515

2020°

20^2020

20°

2 0 "15121515

1513°13

Reduction ofArea, min.

% F

60504055

5050

4055

5050SO

4045

5010

404060

40

40

40

4545°

45°45 f

4040

45°

45°45354545

4545°45

BrinellHardness, max

212255241

293

297297

207192

217217

223

223269331321293

277321235302

NOTES:* See Section 7.8 American Welding Society designation.c Tensile strength 70 ksi [485 MPa] min permitted for extruded shapes.0 Elongation in 2 in. or 50 mm of 12% min and reduction of area of 35% min permitted for cold-finished bars.c Elongation in 2 in. of 12% min and reduction of area of 35% min permitted for cold-drawn or cold-rolled bars.' Reduction of area does not apply on flat bars ' / „ in. [4.80 mm] and under in thickness as this determination is not generally made .in

this product size.c For bars greater than 2 in. [51 mm], a cross section, 60 ksi [105.MPa] min, shall be permitted."Annealed bars shall be capable of meeting the tempered condition requirements when heat treated in accordance with 5.4.3

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SA-479/SA-479M 1992 SECTION II

TABLE 3

RESPONSE TO HEAT TREATMENT

Heat Treatment Temperature _ . . Hardness-F (-Cl.mil Quenehant H R C m | n

403 1750(955) Air 35410 1750(955) Air 35414 1750(955) Oil 42

x Samples (or testing shall be in the form of a section not exceeding % in. (9.50mm) in thicKness.

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PART A — FERROUS MATERIAL SPECIFICATIONS SA-479/SA-479M

SUPPLEMENTARY REQUIREMENTS

The following may be made requirements when the purchaser specifies them tobe applicable.

SI. Materials for High-Temperature Service

Sl . l Unless an H grade has been ordered, this sup-plementary requirement shall be specified for ASMECode applications for service above 1000T [540°C].When invoked, all materials shai! meet the require-ments of the corresponding H grade including chemis-try, annealing temperature, and grain size.

S2. Corrosion Tests

S2.1 Intergranular corrosion tests shall be performedby the manufacturer on sensitized specimens of Types304L, 316L, 321, 347, and 348; and for the other aus-tenitic grades, on specimens representative of the as-shipped condition. All austenitic stainless steels shallbe capable of passing intergranular corrosion tests inthe as-shipped condition. Tests shall be performed inaccordance with Practice E of Practices A 262.

S3. Product Analysis

S3.1 An analysis shall be made by the manufactureron a sample from one bar in each lot as defined inSpecification A 484/A 484M. The analysis shall meet

the requirements of Table 1. Tn the event of failure, thelot represented shall be rejected except that, at theoption of the manufacturer, each bar in the lot maybe tested for acceptance. Product analysis toleranceprovisions do not apply.

S4. Material for High Cycle Fatigue Service

S4.1 The mechanical properties of bars furnished inlengths under 20 ft [6 m] shall be determined by testingone end of each bar. Bars furnished in Lengths of 20 ft[6 m] and over shall be tested at each end.

SS. Material for Optimum Resistance to StressCorrosion Cracking

S5.1 This supplementary requirement is to be refer-enced when austenitic stainless steels are to be pur-chased in accordance with 5.1.1 with solution-annealing as the final operation and with no subsequentcold drawing permitted. Straightening is permitted asa final operation to meet the requirements of Specifica-tion A 484 unless specifically prohibited by the pur-chaser.

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SA-479/SA.-479M 1992 SECTION li

APPENDIX

(Nonmandatory Information)

Xl.l RATIONALE REGARDING DEFINITIONOF SOLUTION ANNEALING IN 5.1.1

Xl.l It is generally recognized that austenitic stain-less steels are solution annealed by heating to a temper-ature that dissolves (takes into solution) chromium car-bides and quenching rapidly so that the chromiumcarbides will not participate in the grain boundarieswhich could cause susceptibility to intergranular corro-sion in a critically corrosive environment. Thus, solu-tion annealing also can be accomplished for non-stabilized grades by taking advantage of hot rollingtemperatures (which always exceed solution annealingtemperature requirements), maintaining hot rollingfinishing temperatures well above minimum solutionannealing requirements, and immediately quenchingintegral with hot rolling. Stabilized grades (with colum-bium or titanium added) cannot be handled this waysince they would become destabilized due to columbi-um or titanium carbide solution, without subsequentreheating.

X1.2 For Boiler Code applications involving temper-

atures where optimum resistance to creep is desired,the larger grain size of material solution annealed byreheating is generally desired. For that reason a mini-mum grain size has been required of the H grades(created for optimum elevated temperature properties)and a mandatory grain size test and report has beenadded for the non-H grades so that the information isavailable for those desiring to reclassify a non-H gradeto H grade.

X1.3 To satisfy the concerns of inadvertent assign-ment of fine grained material to elevated temperatureapplications, special marking has been added for mate-rial which meets the requirements of SupplementaryRequirement SI.

Xl.4 A mandatory test for susceptibility to intergran-ular corrosion has been added for material solutionannealed by the alternative method [see (2) in 5.1.1] sothat a history of data can be accumulated, as has beendone in the past for material solution annealed by re-heating.

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SPECIFICATION FOR BOLTING MATERIALS,HIGH-TEMPERATURE, 50 TO 120 KSI [345 to 827 MPa]

YIELD STRENGTH WITH EXPANSIONCOEFFICIENTS COMPARABLE TO AUSTENITIC

STEELS

SA-453/SA-453M

(Identical with ASTM Specification A 453/A 453M-90)

1. Scope

1.1 This specification covers four grades of boltingmaterials with nine classes of yield strength rangingfrom 50 to 120 ksi [345 to 827 MPa] for use in high-temperature service such as fasteners for pressure vesseland valve flanges. The material requires special pro-cessing and is not intended for general purpose applica-tions. The term "bolting material," as used in this speci-fication, covers rolled, forged, or hot-extruded bars;bolts, nuts, screws, washers, studs, and stud bolts.Headed bolts and rolled threads may be supplied.

NOTE 1—Other bolting materials are covered by SpecificationA 193/A 193M and Specification A 437/A437M.

1.2 Supplementary Requirement SI of an optionalnature is provided. This shall apply only when specifiedby the purchaser in the order.

1.3 This specification is expressed in both inch-poundunits and in SI units. However, unless the order speci-fies the applicable "M" specification designation (SIunits), the material shall be furnished to inch-poundunits.

1.4 The values stated in either inch-pound units orSI units are to be regarded separately as standard.Within the text, the SI units are shown in brackets. Thevalues stated in each system are not exact equivalents;therefore, each system must be used independently of

the other. Combining values from the two systems mayresult in nonconformance with the specification.

2. Referenced Documents

2.1 ASTM Standards:A 193/A 193M Specification for Alloy-Steel and Stain-

less Steel Bolting Materials for High-TemperatureService

A 370 Test Methods and Definitions for MechanicalTesting of Steel Products

A 437/A 437M Specification for Alloy-Steel Turbine-Type Bolting Material Specially Heat Treated forHigh-Temperature Service

E 30 Test Methods for Chemical Analysis of Steel, CastIron, Open-Hearth Iron, and Wrought Iron

E 59 Practice for Sampling Steel and Iron for Determi-nation of Chemical Composition

E 139 Practice for Conducting Creep, Creep-Rupture,and Stress-Rupture Tests of Metallic Materials

12 ANSI Standards:ANSI Bl.l Unified Screw ThreadsANSI B 18.2.1 Square and Hex Bolts and Screws In-

cluding Hex Cap Screws and Lag ScrewsANSI B 18.22 Square and Hex NutsANSI B18.3 Hexagon Socket and Spline Socket Screws

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SA-453/SA-453M 1992 SECTION Q

3. Terminology

3.1 Description of Terms Specific to This Standard:

3.1.1 bolting material — this covers rolled, forged,or hot-extruded bars; bolts, nuts, screws, washers,studs, and stud bolts; and also includes those manufac-tured by upset heading or roll threading techniques.

3.1.2 heat-treatment charge—one heat of materialheat treated in one batch. If a continuous operation isused, the weight processed as a heat-treatment chargeshall not exceed the weights in Table 1.

3.1.3 lot — a lot shall consist of the quantitiesshown in Table 2.

4. Ordering Information

4.1 The inquiry and order shall indicate the fol-lowing:

4.1.1 Quantity (weight or number of pieces),

4.1.2 Type of material (bars, bolts, nuts, etc),

4.1.3 Grade and class,

4.1.4 Method of finishing (see 5.2),

4.1.5 Type of thread desired (see 5.2.2),

4.1.6 Alternative test method option (see 7.2.4.3),

4.1.7 Bolt shape option, if any (see 8.2),

4.1.8 Thread option, if any (see 8.3),

4.1.9 Test method for surface quality, if any (seeSection 10),

4.1.10 Test location option, if any (Section 11),

4.1.11 Rejection option, if any (see 12.1), and

4.1.12 If stress-rupture testing is not required (see7.2.1).

5.2 Finishing Process:

5.2.1 The product shall be hot finished or coldfinished (ground, rough turned or cold drawn) as speci-fied on the purchase order.

5.2J2 Threads may be formed by machining orrolling. For Type 1 bolting, threading shall be per-formed after precipitation heat treatment. For Type2 bolting, threading shall be performed after solutiontreatment but prior to precipitation heat treatment.

5.3 Heat Treatment — Each grade and class shall beheat treated as prescribed in Table 3.

6. Chemical Composition

6.1 Heat Analysis— An analysis of each heat of steelshall be made by the manufacturer to determine thepercentages of the elements specified in Table 4. Thisanalysis shall be made from a test sample taken duringthe pouring of the heat. The chemical composition thusdetermined shall be reported to the purchaser or hisrepresentative and shall conform to the requirementsspecified in Table 4.

6.1.1 Steels with added lead shall not be used.

6.2 Product Analysis:

6.2.1 A product analysis may be made by the pur-chaser from tension samples representing the boltingmaterial.

62J2 Samples for chemical analysis, except forspectro-chemical analysis, shall be taken in accordancewith Practice E 59. The chemical composition thusdetermined shall conform to the requirements for prod-uct analysis variation as specified in Table 4.

6.2.3 A product analysis shall be made by themanufacturer of bar stock made from vacuum-arc re-melted steel.

6.3 Methods of Analysis—For referee purposes, TestMethods E 30 shall be used.

5. Materials and Manufacture

5.1 Melting Process:

5.1.1 The material shall be made by one or moreof the following processes: electric-furnace, inductionfurnace, or consumable-electrode practice.

5.1.2 Vacuum, protective atmospheres, or protec-tive slags may be used during melting or pouring of theheat.

7. Mechanical Properties

7.1 Tension Test:

7.1.1 Requirements— The material shall conformto the room-temperature tensile in each heat-treatmentcharge (Section 3).

7.1.2 Number of Specimens:

7.1.2.1 Heat-Treated Bars — When not more

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PART A — FERROUS MATERIAL SPECIFICATIONS SA.-453/SA-453M

than two sizes of bars are heat treated in the same load,one tension test shall be made from each size in eachheat of material in the heat-treatment charge (see 3.2).When more than two sizes of bare are treated in thesame charge, one tension test shall be made from onebar of each of the two largest diameters from each heatof material in the heat-treating charge.

1.122 Finished Parts — One tension test shallbe made if the lot consists of parts of the same nominaldiameter. If the lot consists of parts of more than onenominal diameter, one tension test shall be made fromeach nominal diameter of each heat involved in the lot(Section 3).

7.1.2.3 The .diameter range shall be in incre-ments of Y2 in. [12.5 mm].

7.1.2.4 Tension Tests are not required on fin-ished parts that are fabricated from heat-treated barsfurnished in accordance with the requirements of thisspecification and tested in accordance with 7.1.2.1, pro-vided they are not given a subsequent heat treatment.

7.1.3 Test Location and Orientation — Specimensshall be taken in accordance with Test Methods andDefinitions A 370, Annex Al, from the bar stock usedto make the product.

7.1.4 Test Methods:

7.1.4.1 The tension test specimen shall be ma-chined to the form and dimensions prescribed in thelatest issue of Test Methods and Definitions A 370.

7.1.4.2 The yield strength shall be determinedby the offset method as described in the latest issue ofTest Methods and Definitions A 370.

7.2 Stress-Rupture Tesf

7.2.1 Requirements — The material shall conformto the stress-rupture requirements prescribed in Table5 for design temperatures above 800°F [427°C]. Materi-al not stress-rupture tested shall be permanentlystamped NR.

12 2 The number of specimens shall be the sameas the required number of tension test specimens.

72.2 The test location and orientation shall be thesame as that required for the tension test specimens.

72A Test Method:

7.2.4.1 The rupture test shall be performed inaccordance with Practice E 139.

7.2.4.2 A combination smooth and notched testspecimen, machined to the dimensions prescribed in

Fig. 1 and Table 6, shall be tested in accordance withthe stress-rupture requirements prescribed in Table 5.The test shall be continued to rupture. The ruptureshall occur in the smooth section of the bar.

7.2.4.3 As an alternative procedure and, whenspecifically approved by the purchaser, separatesmooth and notched test specimens, machined fromadjacent sections of the same piece, with gage sectionsconforming to the respective dimensions of Table 6,may be tested under the above conditions. The notchedspecimen need not be tested to rupture but shall notrupture in less time than the companion smoothspecimen.

7.2.4.4 When the minimum specified time torupture in Table 5 has been achieved, incremental load-ing may be used to accelerate the time to rupture. Atintervals of 8 to 16 h, preferably 8 to 10 h, the stressshall be increased in increments of 5000 psi [34.5 MPa]. ]Rupture location, and elongation requirements shall beas prescribed in Table 5, 7.2.4.2, and 7.2.4.3.

7.3 Hardness Test:

7.3.1 Requirements — The material shall conformto the room temperature hardness requirements pre-scribed in Table 7.

132 Number of Tests:

132.1 Bars 2 in. [50 mm] and Over— One teston each mill-treated length.

12,22 Bars Under 2 in. [50 mm] — One testper bar on at least 10% of the bars.

7.3.3 Test Locations — The hardness test shall bemade at the center of the cross section for bars up to 1in. [25 mm] in diameter, and at the midradius on bars1 in. [25 mm] and larger in diameter.

, 7.3.4 Test Method — The test shall be performedin accordance with Test Methods and Definitions A370.

8. Dimensions and Permissible Variations

8.1 Standard permissible variations in sizes of barsshall be as set forth in Table 8 for hot-rolled bars andin Table 9 for cold-finished bars.

82 Headed bolts shall be semi-finished, hexagonal inshape, and in accordance with the dimensions of ANSIB 18.2.1. Nuts shall be hexagonal in shape, and in ac-cordance with the dimensions of ANSI B 18.2.2. Unlessotherwise specified, the ANSI Standard heavy bolt and

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SA.-453/SA-453M 1992 SECTION It

nut series shall be used. If socket head fasteners are•equired, the dimensions shall be in accordance withANSI B18.3, as specified by the purchaser.

8.3 All bolts, stud bolts, and accompanying nuts,unless otherwise specified by the purchaser, shall bethreaded in accordance with ANSI Bl.l, Class 2A to2B fit, or British Whitworth threads when specified.

8.4 Bolts, screws, studs, and stud bolts shall bepointed. Points shall be flat and chamfered or roundedat option of the manufacturer. Length of point on studsand stud bolts shall be one to two complete threads asmeasured from the extreme end parallel to the axis.Length of studs and stud bolts shall be the threadedlength and shall be measured from first thread to firstthread.

9. Workmanship, Finish and Appearance

9.1 Finished parts shall have a workmanlike finish,maximum 63 fAin. [1.6 fxm] AA on the threads, bodyunderhead fillet, and bearing area.

10. Workmanship and Quality Level Requirements

10.1 The material shall be uniform in quality andfree of defects that would be detrimental to the intendedservice. Such defects may be determined by convention-al test methods, as specified on the purchase order.

11. Inspection

11.1 The manufacturer shall afford the purchaser'sinspector all reasonable facilities necessary to satisfyhim that the material is being furnished in accordancewith the specification. Mill inspection by the purchasershall not interfere unnecessarily with the manufactur-er's operation. All tests and inspections shall be madeat the place of manufacture, unless otherwise agreedto.

12. Rejection and Rehearing

12.1 Rejection — Unless otherwise specified, any re-jection based on tests made in accordance with thisspecification shall be reported to the manufacturerwithin 60 days from the receipt of the material by

the purchaser. Material that shows injurious defectssubsequent to its acceptance at the manufacturer'swork will be rejected and the manufacturer shall benotified.

12.2 Rehearing — Specimens tested in accordancewith this specification that represent rejected materialshall be preserved for 2 months from the date of thetest report. In case of dissatisfaction with the resultsof the test, the manufacturer may make claim for arehearing within that time.

13. Certification

13.1 The producer's certification that the materialwas manufactured and tested in accordance with thisspecification together with a report of the test resultsshall be furnished at the time of shipment. The specifi-cation designation included on test reports shall includeyear of issue and revision letter, if any.

14. Product Marking -'

14.1 Bars— Each lift, bundle, or box shall be proper-ly tagged with durable tags (metal, plastic, or equiva-lent), showing the heat number, type, condition, speci-fication designation (A 453/A 453M), and size.

14.2 Bolts, Nuts, Screws, Studs, and Steel Bolts —Grade and manufacturer's identification symbols shallbe applied to one end of studs % in. [10 mm] in diameterand larger and to the heads of bolts VA in. [6 mm] indiameter and larger. (If the available area is inadequate,the grade symbol may be marked on one end and themanufacturer's identification symbol marked on theother end.) In addition to the identification symbols(grade and class) shown in Table 2, the type designation2 shall also appear on all roll-threaded bolting materialso processed. Absence of the type designation numberindicates Type 1 processed material or machine-cutthreads.

14.3 For purposes of identification marking, themanufacturer is considered the organization that certi-fies the fastener was manufactured, sampled, tested,and inspected in accordance with the specification andthe results have been determined to meet the require-ments of this specification. The specification numbermarked on the material need not include specificationyear of issue and revision letter.

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PART A — FERROUS MATERIAL SPECIFICATIONS SA-453/SA-453M

tH

I ( Ix tF H

1 \

6

rad Detofl Slc*tch

Tr

6O«1JO*

FIG. 1COMBINATION SMOOTH-NOTCH STRESS-RUPTURE TEST SPECIMEN (SEE TABLE 5)

TABLE 1CONTINUOUS HEAT-TREATMENT CHARGE SIZESDiameter, in. |nvn|

To IV. [44]Ovar IV. |44] to 2 ' * [63)Orer 2>A (S3]

TABLE 2LOT SIZES

Oiemetar. in. (mm)

1Vfc(3«i and underO w IV* (38] to IV. (44). ndOver I K (44) to 2% [63]. ndOwer2W(63]

Weight, to [kg]

3000(140016000(2700]

12000(5400]

Maximum UX Sue. b (kg]

200(90]300(140)600(270|20 piaaes

TABLE 3HEAT TREATMENT REQUIREMENTS4

Grade CUss Solution Treatment HjrdcnnQ Traetm«nt

660

651

663

665

Aec

A

8

A

B

A

e

1650 ± 25'F (BOO ± 14*CJ. hokt 2 h. nWi, and Squid quarcft1800 * 25*F (880 ± u*c j . hokJ 1 h. min, and liquid Quench1800 ± 25*F {980 114*C]. hokJ 1 h min. and o« quench

1800 ± 25*F [980 ± 14-CJ. hokJ 2 h. tqjci quench

1950 * 25*F (1065 t WC\. hoW 2 h. io>d quercft

1800 ± 25*F (980 ± 14*C|. hold 3 h. iquid quench

2000 at 25*F [ 1095 * U*CJ. hold 3 h. h*xi quench

1325 * 2S*F (720 ± 14*C]. hold 16 h, air cool1325 ± 25»F (720 ± 14*C), hold 16 h. «r coolU25 ± 25*F (775 ± 14*C) hold 16 h. air cool1200 ± 25*F (550 4 14*C| hold 16 h. air coolhot-ookt worlwd at 12OO*F (650*C| rrtn «v<th 15 X win reductnn in crott-seewxaiare*, ttraw-ratef innejl *t 1200*F [650*C] mr. or 4 h. twihot-cok) worked at 1200*F |650*C| min wfth 15 K rrtn raduction of croet-eectionalan*. ttrMvraief ameel »t 13S0*F (730*C| min tor 4 h. irin1350 to 1400'F |730 to 76O*C1. hold 20 h. kjmaot cool to 1200 at 25*F |650 * 14*C|,hoW 20 h, ai1 COOl1350 to 1400*F (730 to 760*C). hold 20 h. tumaoe oaor to 1200 x 2S*F (650 * 14*Cj.hold 20 h. air cool1350 to 1400*f (730 to 760*C). hold 20 h. fumeoe oool to 1200 ± 25*F [650 *. 14*C|.how 20 h, air eod1350 to 14Q0*F (730 to 760*Cl. hold 20 h. iunaw ooot to 1200 ± 2S*F (650 ± 14*C].hold 20 h. air cool

* Times rater to the minimum time material Is raqurad to be at temperature.

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SA-453/SA-453M 1992 SECTION tl

TABLE 4CHEMICAL REQUIREMENTS

C*rtx>nManganesePhosphorusSulfurSBoonNickelChromiumMolybdenumTungstenTitaniumCofumbium*AluminumVanadiumBoron

Copper

CarbonManganesePhosphorusSulfurSaconNickelChromiumMolybdenumTitaniumAluminumCopperBoron

Content. X

0.06 max2.00 max0.040 max0.030 max1.00 max24.00-27.0013.50-16.001.00-150. . .1.90-2.35

0.35 max0.10-0.500.0010-0.010

. . .

Content,*

0.08 max0.40-1.000.040 max0.030 max0.40-1.0024.00-26.0012.00-15.002.00-3.501.80-2.100-35 max050 max0.0010-0.010

Gred»660

Product AnalyM VarictkxvOver or Under. *

0.01 over0.040.005 over0.005 over0.050200.200.05. . .0.05

0.05 over0.030.0004 under to

0.001 over

Grade 662

Product Analysis. VariationOver or Under. %

0.01 over0.030.005 over0.005 over0.050.200.150.100.050.05 over0.03 over0.0004 under to

0.001 over

Contenc.%

0.28-0.350.75-1500.040 max0.030 max0.30-0.608.00-11.0018.00-21.001.00-1.751.00-1.750.10-0.35025-0.60

050 max

Content. X

0.08 max125-2.000.040 max0.030 max0.10-0.8024.00-28.0012.00-15.00125-2252.70-3.30025 max025 max0.01-0.07

Gnde651

Product Analysis Variation.Over or Under.!

0.020.040.005 over0.005 over0.050.150.150.050.050.05 over0.05. . .

0.03 ovw

Qrade665

Product Analysis Variation.Over or Under, X

0.01 over0.040.005 over0.005 over0.050200.150.100.050.05 over0.03 over0.005

1 Or coiumbum plus tantalum.

TABLE 5STRESS RUPTURE REQUIREMENTS

Grade

660651862865

O a u

A.B, andCAtndBAandBAB

TestTemperature. -

*F(*C|

1200(65011200(65011200[650l1200(650]1200(650)

Stress.

ksi

5640557570

mio

Mf>a

385275380515485

Timelo- Rupture.

mn.h*

100100100100100

55535

* The combination bar specimen shown in fig. 1 site* be ttsled continuously atthe temperature and at the minimum stress specified or at * greater stress andchal rupture in a tone not less than that specified.

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PART A — FERROUS MATERIAL SPECIFICATIONS SA-4S3/SA-453M

TABLE 6TEST SPECIMEN DIMENSIONS

A9:

SpecimenType

123456Tblerance

789101112Tolerance

Mid-lengthGage Dia D andNotch-Root Ola

F

0.1250.1600.1780.2520.3570.505±0.001

3.174.064.526.409.0712.8±0.025

GageLength

G

Inches

0.50.650.751.01 32.0±0.05

Mtlimetres

12.017.020.025.040.0SO.O±1.3

ShoulderDiameter

H

0.1770.2260.2500.3750.5000.750±0.003

4.55.56.59.512.019.0±0.1

Notch-RootRadius

0.0050.0050.0050.007o.oia0.015

±0.0005

0.130.130.130.180.2S0JB±0.01

GENERAL NOTES:* Surfaces marked *, finish to 8 p.ln. [O.Z |un] rms or better.•The difference between dimensions Fand 0 shall not exceed 0.0005 In. CO.Ol mm] for specimens 1 or 2.

The difference shall not exceed 0.001 in. 10.02 mm] for specimens 3, 4, 5, or 6.c Taper the gage length 6 to the center so that the diameter 0 at the ends of the gage length exceeds the

diameter at the center of the gage length by not less than 0.0005 tn. CO.Ol. mm] nor more than 0.0015In. C0.04 mm].

" All sections shall be concentric about the specimen axis within 0.001 In. CO.OZ mm].E Thread size T shall be equal to or greater than diameter H.' Dimensions A and B are not specified.G Length of shoulder C - Y. + »/„ - 0 In. 13.2 + 0.8 mm]." Length of shoulder £ - ' / . + yM - 0 In. CIO.O + 0.8 mm].

TABLE 7MECHANICAL PROPERTY REQUIREMENTS

Grade

660651

662

665

Class

A, B, and CA

B

ABAB

Tensile Strength, min

ksi

130100

95

130125

• 170155

MPa

695690

655

895860

11701070

Yield StrengthCO.2% Offset), min

ksl

es70"60c

6 0 '50c

8580

120120

MPa

58548541541534558S550830830

Elongationfn

.. 4 x Oiam*,min, %

1518

18

15151212

Reductionof Area,min, %

1835

35

18181515

BrinellHardnessNumber

248-341217-277

212-269

255-321248-321311-388311-388

Approximate Rockwell••-•••" Hardness, B and C

rnin- •

99 HRB0-95 HRB

93 HRB

100 HRB"99 HRB32HRC32HRC

max

37HRC29HRC

28 HRC€

35 HRC35 HRC41 HRC41 HRC

•* See Fig. 6 of Test Methods and Definitions A 370.* Material sizes 3 In. [76 mmj and under In diameter. -.c Material sires over 3 In. C76 mmj In diameter. "'••••-.* Conversion numbers taken from Test Methods and Definitions A 370, Table 3D. . '* Conversion numbers taken from Specification A 193/A 193U, Table 2 Caustentticsttels); others by interpolation.

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SA-4S3/SA.-453M 1992 SECTION H

TABLE 8PERMISSIBLE VARIATIONS IN SIZE OF HOT-ROLLED

BARS

. Specified Sire

Vi» ana* underOver V * to Vu. tadOvarV«to lft.lndOver H to 'A. tadOver »A to 1. tact

Over1to1Vfc.tadOveMVbtoiU. tadOvar1VC<to1%,lndOveritt toivi, hdOver1Vfcto2.tad

Over2to2Vk. tadOvar2%to3Vt,tadOver 3% to 4%. tadOver4Vfeto5Vk,tadOverSVfcto6Vfe.tadOvar6Vkto7%.tad

8.0 and underOver 8.0 to 11.0. tadOver 11X to 16.0. tadOver 16.0 to 22.0. aidOvw22Bto25.0.incl

Over 2S.0 to 29.0 MOver 29J0 to 32.0. hdOver 32.0 to 35A.indOver 35J) to 38.0. IndOver 38.0 to 51.0. W

OvarS1J>to«3.0.indOvw 63^) to 99.0. kidOver 89.0 to 114. hdOvar 114 to 140. tadOver 140 to 165. tadOver 165 to 191. tad

Pamvssbie Variation* bomSpecified Size

Over

Inches

0.0050.0060.0070.0080.009

0.0100.0110.0120.014Vu

Vte

v»V MV,V B

Mitrnetrw

0.130.150.1B0^0023

O^S0580.300JJ50.40

040\3.1.6^ 03 i4.0

Under

0.0050.0060.0070.0080.009

0.0100.0110.0120.014V*

000O00

0.130.150.16020023

0250280.300.350.40

00000

. 0

Out of

nouno

0X060X090X100.0120.013

0.0150.0160.0180.0210.023

0X230.0350.0460X580X700.085

0200230250.300.33

0.300.410.46

0.58

0 5 8OX91 21 51JS2 2

TABLE 9PERMISSIBLE VARIATIONS IN SIZE OF

COLD-FINISHED BARS

Pemfesfta Variation from SpecifiedSita, in. [mm]*Specified Size. ta. (mm|

Over Under

Ov*r%to1[13to25].«xd1 to1Vi[25»36l.«xd

0X02 {0X5]0X025(0X6)0.003 [0X8]

0X02 [0X5]0X025 [0X6]0X03 (CX8)

A When k It neoeesery to heat treat or heat treat and piddt after odd Menlng.btcauea of special hardness or mechanical property requirements, t* pemistfcie

• For stta tolerancas of sias over 4 ta. [100 ami the manufacturer *hc<*i be

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PART A — FERROUS MATERIAL SPECIFICATIONS SA-453/SA-453M

SUPPLEMENTARY REQUIREMENT

The following supplementary requirement shall apply only when specified by thepurchaser in the inquiry, contract, and order.

SI. Marking

S1.1 Grade and manufacturer's identification sym-bols shall be applied to one end of studs and to theheads of bolts of all sizes. (If the available area is inade-quate, the grade symbol may be marked on one endand the manufacturer's identification symbol markedon the other end.) For bolts and studs smaller than V4

in. [6 mm] in diameter and for VA in. [6 mm] studsrequiring more than a total of three symbols, the mark-ing shall be a matter of agreement between the purchas-er and the manufacturer.

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SPECIFICATION FOR PRECIPITATION-HARDENING NICKEL ALLOYBARS, FORGINGS, AND FORGING STOCK FOR

HIGH-TEMPERATURE SERVICE

SB-637

(Identical with ASTM Specification B 637-84a)

1. Scope

1.1 This specification covers hot-and cold-worked precipitation-hardenable nickel alloyrod, bar, forgings, and forging stock for high-temperature service (Table I).

1.2 The values stated in inch-pound unitsare to be regarded as the standard.

2. Applicable Documents2.1 ASTM Standards:E 8 Methods of Tension Testing of Metallic

MaterialsE 29 Recommended Practice for Indicating

Which Places of Figures Are to Be Consid-ered Significant in Specified LimitingValues

E 38 Methods for Chemical Analysis ofNickel-Chromium and Nickel-Chromium-Iron Alloys

E 139 Recommended Practice for ConductingCreep, Creep-Rupture, and Stress-RuptureTests of Metallic Materials

E 354 Methods for Chemical Analysis of High-Temperature, Electrical, Magnetic, andOther Similar Iron, Nickel, and CobaltAlloys

3. Descriptions of Terms Specific to This Stand-ard

3.1 bar—material of rectangular (flats), hex-agonal, octagonal, or square solid section instraight lengths.

3.2 rod—material of round solid section fur-nished in straight lengths.

4. Ordering Information

4.1 Orders for material under this specifica-tion shall include the following information:

4.1.1 Alloy (table I).4.1.2 Condition (temper) (Table 4).4.1 J Shape—Rod or bar (round, rectangle,

square, hexagon, octagon).4.1.3.1 Forging (sketch or drawing).4.1.4 Dimensions, including length.

4.1.5 Quantity (mass or number of pieces).4.1.6 Forging Stock—Specify if material is

slock for reforging.4.1.7 Finish.4.1.8 Certification—State if certification is

required (Section 15).4.1.9 Samples for Product {Check)

Analysis—Whether samples for product(check) analysis shall be furnished (9.2).

4.1.10 Purchaser Inspection—If the pur-chaser wishes to witness tests or inspection ofmaterial at the place of manufacture, the pur-chase order must so state indicating which testsor inspections are to be witnessed (Section 13).

5. Chemical Composition5.1 The material shall conform to the re-

quirements as to chemical composition pre-scribed in Table 1.

5.2 If a product (check) analysis is per-formed by the purchaser, the material shallconform to the product (check) analysis varia-tions prescribed in Table 1.

6. Mechanical Properties6.1 Tensile and Hardness Requirements—

The material shall conform to the requirementsfor tensile and hardness properties prescribedin Table 2.

6.2 Stress-Rupture Requirements—The ma-terial shall conform to the requirements forstress-rupture properties prescribed in Table 3.

7. Dimensions and Permissible Variations7.1 Diameter, Thickness, or WUUh—The per-

missible variations from the specified dimen-sions of cold-worked rod and bar shall be asprescribed in Table 5, and of hot-worked rodand bar as prescribed in Table 6.

7.1.1 Out of Round—Cold-worked and hot-worked rod, all sizes, in straight lengths, shallnot be out-of-round by more than one half.thetotal permissible variations in diameter shownin Tables 5 and 6, except for hot-worked rod Vz

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SB-637 1992 SECTION II

in. (12.7 mm) and under, which may be out-of-round by the total permissible variations indiameter shown in Table 6.

7.1.2 Comers— Cold-worked bar shall havepractically exact angles and sharp corners.

7.1.3 Cut Lengths—A. specified length towhich all rod and bar will be cut with a per-missible variation of +to in. (3.18 mm), - 0 forsizes 8 in. (203 mm) and less in diameter or thedistance between parallel surfaces. For largersizes, the permissible variation shall be +V4 in.(6.35 mm), - 0 .

7.1.4 Straightnessfor Cold- Worked and Hot-Worked Rod and Bar—The maximum curva-ture (depth of chord) shall not exceed 0.050 in.multiplied by the length in feet (0.04 mm mul-tiplied by the length in centimeters). Materialunder Vi in. (12.7 mm) in diameter or thedistance between parallel surfaces shall be rea-sonably straight and free of sharp bends andkinks.

7.1.5 For forgings, dimensions and toler-ances shall be as specified on the order, sketch,or drawing.

7.1.6 Dimensions and tolerances for forgingstock shall be as agreed upon between thepurchaser and the manufacturer.

8. Workmanship, Finish, and Appearance8.1 The material shall be uniform in quality

and condition, smooth, commercially straightor flat, and free of injurious imperfections.

9. Sampling9.1 Lot—Definition:9.1.1 A lot for chemical analysis shall consist

of one heat.9.1.2 Mechanical Properties—A lot for ten-

sion, hardness, and stress-rupture testing shallconsist of all material from the same heat,nominal diameter or thickness, or forging size,and condition (temper).

9.1.2.1 For forging stock, a lot shall consistof one heat.

9.1.2.2 Where material cannot be identifiedby heat, a lot shall consist of not more than 500Ib (227 kg) of material in the same size andcondition (temper).

9.2 Test Material Selection:9.2.1 Chemical Analysis—Representative

samples shall be taken during pouring or sub-sequent processing.

9.2.1.1 Product (Check) Analysis shall bewholly the responsibility of the purchaser.

9.2.2 Mechanical Properties—Samples of thematerial to provide test specimens for mechan-ical properties shall be taken from such loca-tions in each lot as to be representative of thatlot

10. Number of Tests10.1 Chemical Analysis—One test per lot.10.2 Tension—One test per lot103 Hardness—One test per lot.10.4 Stress-Rupture—One test per lot

11. Specimen Preparation11.1 Rod and Bar:11.1.1 Tension test specimens shall be taken

from material in the final condition (temper)and tested in the direction of fabrication.

11.1.2 All rod and bar shall be tested in fullcross-section size when possible. When a fullcross-section size test cannot be performed, thelargest possible round specimen shown inMethods E 8 shall be used. Longitudinal stripspecimens shall be prepared in accordance withMethods E 8 for rectangular bar up to Vi in.(12.7 mm), inclusive, in thickness, which aretoo wide to be pulled full size.

11.1.3 Forging stock test specimens shall betaken from a forged-down coupon or a sampletaken directly from stock.

11.2 Forgings:11.2.1 The tension test specimen represent-

ing each lot shall be taken from a forging orfrom a test prolongation.

11.2.2 The axis of the specimen shall belocated at any point midway between the centerand the surface of solid forgings and at anypoint midway between the inner and outersurfaces of the wall of hollow forgings, andshall be parallel to the direction of greatestmetal flow.

11.2.3 The specimens, shall be the largestpossible round-type shown in Methods E 8.

11.3 Stress-rupture specimens shall be thesame as tension specimens except modified asnecessary for stress-rupture testing in accord-ance with Recommended Practice E 139.

12. Test Methods12.1 Determine the chemical composition,

mechanical and other properties of the materialas enumerated in this specification, in case ofdisagreement, in accordance with the followingmethods:

TestChemical AnalysisTensionRounding procedureStress-rupture

ASTM DesignationE 38, E 354''EgE29E139

* Methods E 38 is to be used only for elements not coveredby Methods E J54.

12.2 For purposes of determining compli-ance with the specified limits for requirementsof the properties listed in the following table,an observed value or a calculated value shallbe rounded in accordance with the roundingmethod of Recommended Practice E 29.

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PART B — NONFERROUS MATERIAL SPECIFICATIONS SB-637

Test

Chemical compotitioa,tolerances (when ex-pressed in decimals),•ad hardness

Tensile strength tadyield strength

ElongationRupture life

Rounded Unit for Observed OrCalculated Value

nearest unit ia the last right-hand place of figures of (bespecified limit. If two choicesare possible, as when the digitsdropped are exactly i S or a 5followed only by zeros, choosethe one ending in an evendigit, with sero defined as aseven digit.

nearest 1000 psi (6.9 MP«)

nearest 1%I n

13. Inspection13.1 Inspection of the material shall be made

as agreed upon between the manufacturer andthe purchaser as part of the purchase contract.

14. Rejection and Rehearing14.1 Material that fails to conform to the

requirements of this specification may be re-jected. Rejection should be reported to theproducer or supplier promptly and in writing.

la case of dissatisfaction with the results of thetest, the producer or supplier may make claimfor a rehearing.

15. Certification

tS.t When specified in the purchase orderor contract, a producer's or supplier's certifi-cation shall be furnished to the purchaser thatthe material was manufactured, sampled,tested, and inspected in accordance with thisspecification and has been found to meet therequirements. When specified in the purchaseorder or contract, a report of the test resultsshall be furnished.

16. Product Marking

16.1 Each bundle or shipping container shallbe marked with the name of the material; con-dition (temper); this specification number; thesize; gross, tare, and net weight; consignor andconsignee address; contract or order number,or such other information as may be defined inthe contract or order.

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SB-637 1992 SECTION II

TABLE t CfceaictlRcqaktaeats

Element

CarboeMangaaeseSilkenPhosphorusSulfurOuoQuoxnCobaltMolybdenumTitiaiomAlutntsumZirconiumBorooIronCopperNkkd

CarbccMangueseSilicoaPhosphorusSulfuiChroc&iumCobaiMolybdenumColuoiSum •*• un-

utuaTitaniwnAluminumBoroolroaCoppcNickel

CarbonMao£ueseSiliconPbospbOTUSSulphurCbroawumCobih'MolybdenumCoiumbium +

TunxlumTlunjumAluaufiumBorooIroaCopperNkke^

Compositionlimits, %

Product (Check) Analysis Varia-tions, under miu or over max, ofthe Specified limit of Element

UNS N07252 (Formerly Grade 689)

0.10-0.200.50 max0.50 max0.015 max0.015 max18.00-20.009.00-11.009.00-10.502.25-2.750.75-1.25

0.003-fl.Ol5.00 max

remainder*

0.010.03"0.030.0050.0030.250.10 under min, 0.1 S over mix0.150.070.10

0.0020.07

UNS NO75OO (Formerly Grade 684)

0.15 max0.75 max0.75 max0.015 max0.015 max15.00-20.0013.00-20.003.00-5.00

2.50-3.252.50-3.250.003-0.014.00 max0.15 maxremainder*

0.010.030.050.0050.0030. IS under min, 0.25 over max0. IS under min, 0.20 over mix0.10

0.070700.0020.070.02. . .

UNS N07718 (Formerly Grade 718)

0.08 max0.35 max0.35 max0.015 max0.015 max17.0-21.01.0 max2.80-3.304.75-530

0.65-1.150.20-0.800.006 maxremainder"4

0.30 max50.0-55.0

0.010.030.030.0050.0030750.030.05 under min, 0.10 over max0.15 under min. 0.20 over max

0.04 under min, 0.05 over max0.05 under mia, 0.10 over ttux0.002

0.030.35

Competitionlimits, %

Product (Check) Analyst Varia-tions, under min oc over max, ofthe Specified Limil of Element

UNS N07001 (Formerly Grade 6X5)

0.03-0.101.00 max0.75 max0.030 max0.030 max18.00-21.0012.00-15.003.50-5.002.75-3.251.20-1.600.02-0.120.003-0.012.00 max0.50 maxremainder^

0.010.030.050.0050.0050.250.150.100.070.100.01 under min, 0.02 over max0.0020.050.03

UNS NO775O (Formerly Grade 688)

0.0S max1.00 max0 JO max

0.01 max14.00-17.00l.OOmax"

0.70-1.20

2.25-2.750.40-1.00. . .5.00-9.000 3 0 max70.00 min c

0.010.030.03

0.0030.15 under mio, 0.25 over maji0.03

0.05

0.070.05 under min, 0.10 over max

0.100.030.45

UNS NO7O8O (Formerly Grade 80A)

0.10 max1.00 max1.00 max

0.015 max18.00-21.00-

1.80-2.70030-1.80

3.00 max

remainder*

0.010.030.05

0.0030.25

0.05 under mia. 0.07 over max0.05 under min, 0. EO over max

0.07

A Tfee elenn" If cetermined.c Ntciel + cobalt.

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PART B — NONFERROUS MATERIAL SPECIFICATIONS SB-637

TABLE 1 TanBe nmi HaHaeu Requirements*

Alloy

N07252

N07001

N07500 (rod and bar)

N07500 (forgings)

N0775O Type 1

N0775O Type 2C

N07750Type2°

MO775OType3

NO77I8

NO7O8O

Heat Treatment

solution + precipitation harden

solution 4- stabilize 4- prccipi-talion harden

anneal + solution 4- stabilize+ precipitation harden

solution + stabilize + precipi-tation harden

solution at 2IOO°F (1I49°C)+ stabilize 4- precipiutioo

solution it I8OO°F (982°C) 4-precipitation harden

solution at 1800T (982'C) +precipitation harden

solution anneal at 2O00'F<IO93"C) + precipitationharden

solution + precipitation harden

solution + stabilize + precipita-tion harden

TensileStrength,min, pji(MPa)

160 000(1100)160 000(1100)175 000(IM5)170 000(1170)140 000(965)

170 000(1170)170 000(1170)160 000(1103), min185 000(1276), max185 000(1275)135 000(930)

YieldStrength (0.2

% offset),rain, psi(MPa)

90 000(620)110 000(760)I0S 000(725)100 000(690)

90 000(620)

115 000(790)115 000(790)100 000(689), min130 000(896), mat150 000(105)

90 000<*20)

Elonga-tion in 2in.(50mm) or

AD, min.%

20

15'

15

20

8

IS

15(10)*20

12(6)1

20

Reductionof Area.min. %

18

18"

15

18

IS

15(\2f20

15

BrinellHardness

310 min

310 min

310 min

310 min

262 min

302 to 363

302 to 363

267-363.Bm

27-40, Re

331 min

* The supplier shall demonstrate that the material will meet fatly beat-Created properties after full heat Ireatment inaccordance with Table 4.

* Forging*.p Up to 2.50 in. (63.5 mm), exclusive." 2.50 to 4.00 in. (63 J to 101.6 mm), exclusive." These values apply for tension specimens machined langentially from near the center of Urge disk forgings over 50 in.'

in cross section or radially from rings 3 in. (76.2 mm) or more in thickness.

TABLE 3 Stress-Rupture Re*tk«»enrs*

Alloy Heal TreatmentTest Tem-

perature, *FCO

Stress, psi(MPa)*

MinimumHours

Elongation in 2 in.or 50 mm (or 4 0 ) ,

min, %

N07252

N07001

N075O0 (rod and bar)

N075O0 (forgings)

N07750 Type 1

N077I8

N07080

solution + precipitation harden

solution 4- stabilize 4- precipitationharden

anneal 4- solution 4- stabilize +precipitation harden

solution 4- stabilize 4- precipitationbarden

solution at 2IO0°F (1149"C) 4- su-bilize 4- precipitation harden

solution 4- precipitation harden

solution 4- stabilize 4- precipitationharden

1500(816)1500(816)1500(816)1500(816)1350(732)1200(649)1400(760)

30 000(205)

33 000(230)

38 000(260)

38 000(260)

45 000(310)

100 000(690)

47 000(325)

100

100

too

100

100

23

23

10

5

5

S

5 (3 if hours exceed136)

5

3J

* The supplier shall demonstrate thai the material will meet fully heat-treated properties after full heat treatment inaccordance with Table 4.

' Test specimens meeting minimum requirements may be overloaded to produce rupture in a reasonable and practical timeperiod.

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SB-637 1992 SECTION II

TABLE 4 Heat Tmbaeat*

Alloy

Recom-mended An-

nealingTreatment

Recommended Sohi-lioo Treatment

Recommended Sta-bilizing Treatment

Precipitation Harden-ing Treatment

N07252

N070O1

NO75O0

N07750 Type 1(Service above1IOO°F)(593°C)

N07750 Type 2(Service up toH00°F)(593°C)

NO7750 Type 3

N077I8

NO7O80

2150 ± 25"F(1177 ±I4°C). bold 2h. air cool

(oars only)

1950 ± 25*F (1066 ±I4*C), hold 4 b. air cool

1825 to 1900*F (996 toi036°C).hotd4h,oilorwater quench

1975 ± 25'F (1080 ±14'C). hold 4 h, air cool

2100 ± 25°F (1149 ±iVC).hold2to4h,a ircool

1800 ± 25°F (982 ±I4°C), hold Y> h min.cool at rate equivalentto air cool or faster

I975-2O5O*F(IO79-1I2I*Q, hold 1 to 2 h.air cool

1700 to I85OT (924 to10l0"C), hold 'A h min.cool at rate equivalent toair coot or faster

1950 ±25*F( 1066 ± WQ,hold 8 h. air cool

1550 ± 25'F (843 ±I4°C), hold 4 h, aircool

1550 ± 25°F (843 ±14-C). hold 24 h.air cool

1550 ± 25*F (843 ±WC). hold 24 h.air cool

1560 ± 25T (849 ±14*O, hold 24 h. sircool

1403 ± 25°F (750 ±14-C). hold 15 h, aircool or furnace cool

1400 ± 25°F (760 ±I4°C), hold 16 h, aircoot or furnace cool

1400 ± 25°F (760 ±14°C), hold 16 h. aircool or furnace cool

!30O±25°F(7O4:t 14'C)hold 20 h. air cool orfurnace coot

1350 ± 25°F (732 ±14 °C). hold 8 h. furnacecool to 1150 ± 25"F(621 ±I4°C). hold untiltoul precipitation heattreatment h u reachedIB h, air cool

l30O±25*F(7O4± \*XXhok) 20 h, + 4 - 0 h, aircool

1325 ± 2 5 T (718 ± I4"Q,hold at temperature for 8h, furnace cool to 1150 ±25T(62I ± I4*Q, hoWunlit tout precipitationheat treatment time hasreached 18 h, air cool

1290 ± 25T(699± 14'Q,hold 16 h. air cool

* The purchaser shall designate on the purchase order or inquiry any partial stage of heat treatment required on materialto be shipped.

TABLE S Permissible Vtrillions in Diameter or EHstaace Betwee* Parallel Surfaces of CoM-Worted Rods and Bars)

Permissible Variations from Specified Dimension, in.(mm)Specified Dimension, in. (mmf*

Plus Minus

Rods:K.io*i«(l.59lo4.76),excltt.to Vi (4.76 to 12.70), exelV, u> % (12.70 to 23.81), indOver '«« to l%s (23.81 to 49.2), inclOver I'Vis to 2W (49.2 to 63.5), incl

Bars:K.toK»(l.59to4.76),exdMt to 14 (4.76 to 12.7), exd

00

0.001 (0.025)0.0015 (0.038)0.002 (0.051)

00

0.002(0.fJ5l)0.003 (0.076)0.002(0.051)0.003 (0.076)0.004(0.102)

0.002(0.051)0.003 (0.076)

A Dimensions apply to the diameter of rods, to the distance between parallel surfaces of hexagonal, octagonal, and squarebar, and separately to width and thickness of rectangular bar.

TABLE « PenttSsMe Variation hi Go-tut m Dbtaacc Bettreea Paraftd Surfaces of Ho<-Worte* R o * mm* Bmn

Specified Dimension, in. (mm)'

Permissible Variations from Specified Dimension, in.(mm)

Rod and bar, bot-finisbed:I (25.4) and underOver 1 to 2 (25.4 to 50.8). mdOver 2 to 4 (50.8 to 101.6), indOver 4(101.6)

Rod, bot-fuiishod and rough-turned or ground:Under 1 (25)1 (25) and over

+

0.016(0.406)0.031 (0.787)0.047(1.19)0.125(3.18)

0.005(0.13)0.031 (0.79)

-

0.016(0.406)0.016 (0.406)0.031 (0.787)0.063(1.60)

0.0O5(O.t3)0

•* Dimensions apply to the diameter of rods, to the distance between parallel surfaces of hexagonal, octagonal, and squarebar, and separately to width and thickness of rectangular bar.

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INIS

KAERI/AR-561/2000

(AR,TR

2000. 3.

p. 78 a O ), 21X29.7 Cm.

OO TT

.a.

3.5L£\5L

. Baffle/FormerirMS

1131^ 7ov, control rod guide tube split pin-tr Alloy X-750, core support system

^ A286 ^°1^ 7l^la| lp3 - -Ir

Page 87: 3.1/40 - International Nuclear Information System · 2004. 12. 24. · damage nuclear fuel and limits the operation of nuclear reactor. In foreign reactors operated more than 10 years,

BIBLIOGRAPHIC INFORMATION SHEET

Performing Org.Report No.

Sponsoring Org.Report No

Standard Report No. INIS Subject Code

KAERI/AR-561/2000

Title / Subtitle Degradation of fastener in reactor internal of PWR

Project Managerand Department(or Main Author)

D. W. Kim, Nuclear Materials Technology Development Team

Researcher and

Department

W.S. Ryu, J.S. Jang, S.H. Kim. W.G. Kim,M.K. Chung, C.H. HanNuclear Materials Technology Development Team

Publication

PlaceTaejon Publisher KAERI

Publication

Date2000. 3.

Page p. 78 111. & Tab. Yes(O), No ( ) Size 21 X 29.7cm.

NoteClassified Open(O), Restricted( ),

Class DocumentReport Type State of the Art Report

Sponsoring Org. Contract No.

Abstract (15-20 Lines)

Main component degraded in reactor internal structure of PWR is fastener

such as bolts, stud, capscrew, and pins. The failure of these components may

damage nuclear fuel and limits the operation of nuclear reactor. In foreign

reactors operated more than 10 years, an increasing number of incidents of

degraded thread fasteners have been reported. The degradation of these

components impair the integrity of reactor internal structure and limit the life

extension of nuclear power plant. To solve the problem of fastener failure, the

incidents of failure and main mechanisms should be investigated. The purpose of

this stat-of-the-art report is to investigate the failure incidents and mechanisms

of fastener in foreign and domestic PWR and make a guide to select a proper

materials.

There is no intent to describe each event in detail in this report This report

covers the failures of fastener and damage mechanisms reported by the

licensees of operating nuclear power plants and the applicants of plants

constructed after 1964. This information is derived from pertinent licensee event

reports, reportable occurrence reports, operating reactor event memoranda, failure

analysis reports, and other relevant documents.

Subject Keywords(About 10 words)

Internal, Bolt, Split pin, Stud