SAFELIFE contribution to R&D

on WWER RPV

 EC-JRC-Institute for Energy, Petten, The Netherlands

L.Debarberis, C. Rieg

01-0

6-26

-2-G

C-BM

S

1

Ukrainian-Hungarian ConferenceApril 2006, Hungary

7 Institutes in 5 Member States:JRC - Joint Research Centre

IE - Petten The Netherlands- Institute for Energy

IRMM - Geel Belgium- Institute for Reference Materials and Measurements

ITU - Karlsruhe Germany - Institute for Transuranium elements

IPSC - IHCP - IES - Ispra Italy - Institute for the Protection and the Security of the Citizen - Institute for Health and Consumer Protection - Institute for Environment and Sustainability

IPTS - Seville Spain- Institute for Prospective Technological Studies

North-West - Holland

4

Petten site

> 100 LWRs in EU ~ 100 GWe produced Ageing of plants - Safe Operation (3S) Needs for integrated view of PLIM EU Enlargement Optimisation of PLIM R&D

Background24

45

135

87 88

43

20

0

20

40

60

80

100

120

140

Number

OfNPPs

6-10 11-15 15-20 21-25 26-30 >30

Age (2000)>35 years

European Union new strategic goal

“to become the most competitive and dynamic knowledge-based economy

in the world capable of

sustainable economic growth”

Towards Sustainable Nuclear Fission Energy

March 2000, Lisbon European Council

European Platform for FISSION

01-0

6-26

-2-G

C-BM

S

7

EU PLIM Activities

COVERS C.A.

DG RTD

PERFECT I.P.

PLIM NoEProposal (NULIFE)

TACIS-TAREG

Joint Research CentreSAFELIFE & European Networks

(AMES, etc.)

01-0

6-26

-2-G

C-BM

S

8

EU PLIM Activities

Joint Research CentreSAFELIFE & European Networks

(AMES, etc.)

 

Plant Life Management Issues

RPV Lifetime assessment- embrittlement, fracture assessment- ISI, RPV cladding- VVER specific

- mitigation measures, annealing- re-embrittlement

SAFELIFE

JRC-IE Capital FacilitiesHigh Flux Reactor (HFR)45 MW Research Reactor

SAFELIFE

Stress-corrosion

Other key FacilitiesPositron annihilation

Plant Life Management Issues

key components other than RPV; including:- Primary piping, pressuriser,thermal fatigue, DMW- Internals (SCC)- SG, concrete, cables, etc.

 

SAFELIFE

Effectiveness of European Networks INTEGRATION & BARRIERS BREAKING GLOBAL PLANNING - ‘EUROPEAN’ SCALE SOLUTION OF GLOBAL ISSUES TECHNOLOGY TRANSFER STRONG CO-OPERATION WITH IAEA REDUCTION OF DUPLICATION

SAFELIFE

( RB

NET

NESC

ENIQ ,

JRC European Networks

European Networkson Nuclear Safety

SAFELIFE

SAFELIFE

AMESAMALIA

SENUF

NESC-IV

VERSAFE

ATHENA

VERLIFE

JRC European Networks

DG RTD Thematic Networks

( RB

NET

NESC

ENIQ

European Networkson Nuclear Safety

SAFELIFE

SAFELIFE

AMESAMALIA

SENUF

NESC-IV

VERSAFE

ATHENA

VERLIFE

NESC-IPISA

REFEREE

MODEL ALLOYS

ENUKRANESC-II

NESC-III

SMILE

DISWEC

IRLA

VOCALIST

THERFAT

AMES NDT

AMESDosimetry

MADAME

RESQUE

SPIQNAR

BIMET

VORSAC

INTERWELD

ADIMEW ENPOWER

RESTAND

VAMAS TWA20

COBRA

REDOS

GRETE

FRAME

IASCC & NRTD within PECO

JRC European Networks

DG RTD Thematic NetworksDG RTD Shared Cost &nIn-kind Actions

( RB

NET

NESC

ENIQ

AMESAMALIA

European Networkson Nuclear Safety

SAFELIFE

SAFELIFE

SENUF

Plant Life Management Issues

 

- Improved integrity assessment:DT/NDT & numerical modelling:- Evaluation & monitoring of degradation & stresses - Large-scale European benchmark - reliability models- Risk-based approaches - Human performance enhancement- Safety Culture

SAFELIFE

Nuclear EU+CH

PWR

BWR

GCR

COVERS Co-ordination Action“Establish a viable RTD structure with a view to enhance the scientific

and technical cooperation of actors involved in VVER safety research … (utilities, manufacturers, regulatory bodies, users)”.

EU operate VVER units (440 and 1000 MW)Units in operation/construction in Ukraine and RussiaOperation of all units was safe and efficientNational supporting technical organisations / National R&D

• maintain and improve safety • common database - “good practice”• identify/initiate required RD• strengthen links - exchange of information• knowledge management & dissemination platforms• harmonised Safety Culture• cooperation with ISTC (Ukraininan / Russian org.)

COVERS Co-ordination Action

General objectives of CA:

SOME CONTACTS / LINKS:

SAFELIFE: JRC; L. DebarberisTACIS-TAREG: JRC; M. Bieth/C.Rieg PERFECT I.P.: EDF; J-P MassoudCOVERS C.A.: NRI; I. VasaNULIFE NoE: VTT, R.Rintama Nuclear Platform: CEA Direction

www.jrc.nlwww.jrc.nl/SAFELIFE http://projects-2006.jrc.cec.eu.int

01-0

6-26

-2-G

C-BM

S

SAFELIFE recent resultsOn RPV embrittlement modelling

01-0

6-26

-2-G

C-BM

S

24

EmbrittlementMechanistic framework

MD(,T,Ni) PRE(,Cu,T,Ni, rate,Mn)SEG(,T,P,Ni, rate)………..

qualitative

quantitativeRadiation Embrittlement Understanding for PLIM Activities at EC-JRC-IEDebarberis, Sevini, Acosta, Pirfo, Bieth, Weisshaeupl, Törrönen, Kryukov & ValoInternational Journal Strength of Materials, ISSN 0556-171X, No. 1 (367) 2004

Damage = (MD, PRE, SEG, …)

MD(,T,Ni) PRE(,Cu,T,Ni, rate,Mn)SEG(,T,P,Ni, rate)………..

- linear summation- quadratic option- synergisms

aDBTTshift

direct matrix damage

) /

(1 eb Sat

precipitations

)] - c02

(2/12/1[1c

Tanghc start

segregations

n

Fluence, n cm-2

DB

TT

SH

IFT

, °C

0

20

40

60

80

100

120

140

160

180

200

1.00E+18 5.10E+19 1.01E+20 1.51E+20 2.01E+20

TOTAL

Precipitation (Cu))

segregation (P)

Direct matrix damage

Semi-mechanistic analytical model for radiation embrittlement and re-embrittlement data analysis International Journal of Pressure Vessels and Piping, Volume 82, Issue 3, March 2005, 195-200 Debarberis, Kryukov, Gillemot, Acosta and Sevini

0

50

100

150

200

250

0.00 40.00

L Cu

H Cu

VH Cu

Fluence, 10 18 n cm-2

DB

TT

SH

IFT

, °C

HFR data Kola data

Cu up to ~ 1 wt%

80.00

0

50

100

150

200

250

300

0.00 40.00 80.00

L Cu & H P

H Cu & H P

VH Cu & H P

VH Cu & M P

Fluence, 1018 n cm-2D

BT

T S

HIF

T, °C

HFR data Kola data

P up to ~ 0.04 wt%

)](1[2

)/

(1 11

5.0

dTanh

PceCubaDBTT startsat

shift

model alloys – low Ni

Irradiation embrittlement of model alloys and commercial steels: analysis of similitude behaviorDebarberis, Sevini, Acosta, Kryukov, Nikolaev, Amaev, ValoInternational Journal of Pressure Vessel and Piping; 79 (2002) 637-642

)](.5.5[1c2

Tanghc start

R2 = 0.991

0

40

80

120

0 0.05P, wt%

Seg

reg

atio

np

aram

eter R2 = 0.991

0

40

80

120

0 0.05P, wt%0

100

200

300

400

0 100 200 300 400

Kola - low NiLYRA-HFR; low Ni

Mea

sure

d D

BT

T S

hif

t , °

C

Calculated DBTT Shift , °C

model alloys – low NiHFR-LYRA + KOLA

Use of the Semi-Mechanistic Analytical Model to Analyse Radiation Embrittlement of M.A.: Cu and P Effects Debarberis, Kryukov, Gillemot, Valo, Morozov, Brumovsky, Acosta, SeviniIntern. Journal of Problems of Strengths, ISSN 0556-171X, UDC 539.4, 2004, No.3.`

) / (1 eb Sat

0

80

160

0 1.2Cu, wt%

Pre

cip

itat

ion

par

amet

er R2 = 1

0

80

160

0 1.2Cu, wt%

R2 = 1

][

All welds

0 30 60 90 120 150 180 210 240

0

30

60

90

120

150

180

210

240

Tk

, CoM

ea

sure

d

Tk

, Co

Calculated

63 points

VVER 440

Evaluation of WWER – 440 radiation embrittlement data using the semi-mechanistic model Zhurko, Krasikov, Kryukov, DebarberisIAEA Specialist Meeting on Radiation Embrittlement, Gus, Russia, May 2004

0.240.055Cu

0.0450.010P

Max, %Min,%

- 63 points- 19 welds- high flux data- 3.5 to 60·1019 n/cm2

Advanced Methods for VVER RPV Embrittlement Assessment Debarberis, Kryukov, Erak, Kevorkyan and Zhurko;International Journal of Pressure Vessel and Piping, Elsevier, (2004); 81/8:695.

0

20

40

60

80

100

120

140

160

180

200

5.E+19 1.E+20 2.E+20 3.E+20 4.5E+20

DB

TT

SH

IFT

, D

C

Re- embrittlementafter annealing

annealing

Primary embrittlement

Re-embrittlementRe-embrittlement

0 5 10 15 20 25 300

50

100

150 Re-embrittlement of VVER-440 welds (P=~0.04 wt%)

DB

TT S

hif

t, oC

fluence, x1018cm-2, E>0.5 MeV

Advanced Methods for VVER RPV Embrittlement Assessment Debarberis, Kryukov, Erak, Kevorkyan and Zhurko;International Journal of Pressure Vessel and Piping, Elsevier, (2004); 81/8:695.

Fluence

P=0.038 P=0.048

0 20 40 60 80 100 120 140 160 180 2000

20

40

60

80

100

120

140

160

180

200

P=0.033welds

DBTT Calculated, ºC

DB

TT

mea

sure

d,

ºC

VVER RPV embrittlement - effect of Nickel at 1.2 and 1.7 wt%trends from Surveillance, Tacis & other programmes data

0

20

40

60

80

100

120

140

160

0 30 60 90 120 150 180

Fluence, 10 18 n cm -2 (E>0.5 MeV)

DB

TT

sh

ift,

°CTAC-3

TAC-4

SS SU-1 R-3

Ni=1.7 wt%

ED-3

TAC-2

SS NV-5 Z2

Ni=1.2 wt%

CF=20

Ni=1.7 wt%

High Nickel

Low Nickel

Ni=1.2 wt%

Mechanistic interpretation & forecasting of radiation damage of high Ni RPV materials data Debarberis, Acosta, F.Sevini, Kryukov and Zhurko - IAEA Specialist Meeting on Radiation Embrittlement, Gus, Russia, May 2004

0

100

200

300

400

0 20 40 60

fluence value, 1018 n cm-2 (E>0.5 MeV)

DB

TT

Sh

ift ,

°C

Ni=1.2 wt %Cu= 0.4 wt%, P=0.009 wt%

Ni=0.004 wt %Cu= 0.41 wt%, P=0.012 wt%

Ni

model alloysHFR KOLA

Role of nickel in a semi-mechanistic analytical model for radiation embrittlement of model alloys Journal of Nuclear Materials, Volume 336, Issues 2-3, 1 February 2005, Pages 210-216 Debarberis, Acosta, Sevini, Kryukov, Gillemot, Valo, Nikolaev, Brumovsky

0

100

200

300

400

0 100 200 300 400

Kola - low Ni

LYRA-HFR - low Ni

high Ni (HFR+Kola)

Mea

sure

d D

BT

T S

hif

t , °

C

Calculated DBTT Shift , °C

aDBTT shift = + )](.5.5[d

Tanghc start

1/2 / 1 eb Sat

--+ ( )

b = b1*Cu c = c1*Pf(Ni)

Ni inclusion in semi-mechanistic analytical model for Radiation embrittlement of model alloys and combined effects with Cu and P - Debarberis, Kryukov, Gillemot, Valo, Nikolaev, Brumovsky, Acosta & Sevini, IAEA Specialist Meeting Radiation Embrittlement, Gus, Russia, May 2004

0

20

40

60

80

0 10 20 30fluence value, 1018 n cm-2 (E>0.5 MeV)

DB

TT

Sh

ift, °

C

Low Ni

Guide, CF=20

High Ni & MnHigh Ni – Low Mn

Mn effect

Extended analysis of VVER-1000 surveillance dataInternational Journal of Pressure Vessels and Piping, Volume 79, Issues 8-10, August 2002, 661-664 Kryukov, Erak, Debarberis, Sevini and Acosta

”Comparison of Nickel Effects on Embrittlement Mechanisms in Prototypic WWER-1000 and A533B Steels"; R.K. Nanstad, M.A. Sokolov, M.K. Miller, and G.R. Odette - ORNL - UCSB

100 ?

Precipitations

Fluence, n cm-2

DB

TT

SH

IFT

, °C

Mn-Ni

EUR 21304 EN

IAEA CRP-10 in preparation (Mn-Ni)

VVER-1000Model AlloysPWR welds

Mechanistic interpretation & forecasting of radiation damage of high Ni RPV materials data Debarberis, Acosta, F.Sevini, Kryukov and Zhurko - IAEA Specialist Meeting on Radiation Embrittlement, Gus, Russia, May 2004

01-0

6-26

-2-G

C-BM

S

ENUKRA

IRLA

ATHENA

AMES

Magnetic Methods, etc.

JRC – Ukrainian OrganisationsExample of Co-operations

01-0

6-26

-2-G

C-BM

S

ENUKRAImplementation of modern methods for fracture mechanics testing and transfer of western countries knowledge and experience to Ukrainian engineer relating to RPV metal condition assessment.

TPC Programme

01-0

6-26

-2-G

C-BM

S

ENUKRA project

TPC Programme

TECNATOM, S. A - SpainNUCLEAR RESEARCH INSTITUTE - Ukraine JRC-IE - The NetherlandsNRG - The Netherlands

ATHENA - AMES

Ukrainian organizations• Institute for Problems of Strength, NAS (Kiev) • Institute of Nuclear Research, NAS (Kiev) • Welding Institute, NAS (Kiev) • Physico-Mechanical Institute, NAS (Lviv) • “Kharkov Physico-Technical Institute (Kharkov)

Tractebel Suez (B)JRC IE (NL)AEA Technology (UK)AEKI (H) CEA (F)CIEMAT (S)EDF (F)FZR (G)NRG (NL)SCK.CEN (B)Tecnatom (S)Empresarios Agrupados (S)University of Cantabria (S)Framatome ANP GmbH(G)Rolls Royce (UK)British Energy (UK)BNFL Magnox Electric plc (UK)LMD Consultancy (UK)NRI Rez (CZ)VTT (FIN) IMS (BG), VUJE (SK), Skoda (CZ)Russian Research Center “Kurchatov Institute” (Moscow), CNIIKM “Prometey” (Saint Petersburg), OKB “Gidropress” (Moscow)

01-0

6-26

-2-G

C-BM

S

TPC Programme

TECNATOM, S.A – Spain JRC - The NetherlandsNuclear Research Institute – UkraineInst. for Problems of Strength - Ukraine NRG - The NetherlandsKurchatov Institute – Russia

IRLATransfer western countries knowledge & experience related to RPV residual life assessment, and check surveillance progs

IRLATransfer western countries knowledge & experience related to RPV residual life assessment, and check surveillance progs

THANKS!

01-0

6-26

-2-G

C-BM

S

Wish you a fruitful conference, pleasant stay & social programme

Ukrainian-Hungarian ConferenceApril 2006, Hungary