Application of the FENDL-3 Test Data Library to IFMIF

KIT – University of the State of Baden-Wuerttemberg and National Research Center of the Helmholtz Association

Institute for Neutron Physics and Reactor Technology

www.kit.edu

Application of the FENDL-3 Test Data Library to IFMIF

U. Fischer, K. Kondo, A. Serikov, P. Pereslavtsev

23rd Research Coordination Meeting on FENDL-3, IAEA, Vienna, December 6 – 9, 2011

Overview

Test application of FENDL-3 neutron data library for IFMIF neutronics calculations

Use of McDeLicious-11 Monte Carlo code and a new detailed Test Facility model converted from CAD by McCad software

Calculations of n- and g-fluxes, nuclear heating, gas production and displacement damage in test rigs (Eurofer specimens)

Shielding calculations for assessment of biological dose rate behind thick concrete walls during operation

Comparison of nuclear responses calculated with FENDL-3 (SLIB-R2) and the standard IFMIF library

Comparison of relevant cross-section data extracted from ACE data library

U. Fischer, KIT, FENDL-3 Test Application to IFMIF


CAD Model of IFMIF Target and Test Cell (TTC) including vessel, Target assembly, concrete cover, Test Modules and pipes (2010)



LFTM

Graphite

Liquid Lithium

HFTMCFTM

Moderator (Tungsten)

TRTM

D beam

Total: 17520 cells, 3243 surfaces

Converted IFMIF TTC model visualised by MCNP plotter (2D cuts)

Target and Test Module Region Full TTC model



250 cm

Access cell

Access/Maintenance Room

Access cell floor

Test cell ceiling

400 cm

Dedicated TTC model for IFMF shielding calculations



Beam level

Specimen (Eurofer & NaK filling)Lithium Target

HFTM

Eurofer: NaK = 74:26 (volume ratio)Na:K = 22:78 (weight ratio)

IFMIF TTC model: HFTM module section (vertical cut)



8.1 cm

Beam footprint

Beam level

Specimen (Eurofer & NaK filling)

Heater (Eurofer & NiCr)

IFMIF TTC model: HFTM module front view (vertical cut)



Graphite

Lithium Target

HFTM

Specimens of CFTM

W moderator

TRTM

MFTM

d-beam

LFTM

IFMIF TTC model: Target, HFTM, MFTM and LFTM moduled (horizontal cut)



Standard IFMIF Data Library vs. FENDL-3/SLIB, release2 : Sources of Data Evaluations

Element I sotope Standard IFMIF- library

FENDL/SLIB-3R2 library

Hydrogen

Lithium

Beryllium Oxygen Sodium

Magnesium Aluminum

Silicon

Sulfur Potassium

Calcium

Titanium

1 2 6 7 9 16 23 24 27 28 29 30 32 39 40 42 43 44 46 48 46 47 48 49 50

LA150 LA150 INPE INPE LA150 LA150 INPE

ENDF60 LA150 LA150 LA150 LA150

ENDF/B-VI INPE

LA150(nat)

JNDFFXS2 JNDFFXS2 JNDFFXS2 JNDFFXS2 JNDFFXS2

ENDF/B-VI I ENDF/B-VI I ENDF/B-VI I ENDF/B-VI I ENDF/B-VI I ENDF/B-VI I JENDL-HE JENDL-HE JEFF-31

ENDF/B-VI I ENDF/B-VI I ENDF/B-VI I ENDF/B-VI I ENDF/B-VI I JENDL-HE JENDL-HE JENDL-HE JENDL-HE JENDL-HE JENDL-HE JENDL-HE JENDL-HE JENDL-HE JENDL-HE JENDL-HE

Element I sotope Standard IFMIF- library

FENDL/SLIB-3R2 library

Chromium

Vanadium I ron

Nickel

Copper

Tungsten

50 52 53 54 51 54 56 57 58 58 60 61 62 64 63 65 182 183 184 186

LA150 LA150 LA150 LA150 INPE LA150 LA150 LA150 IEXS2 LA150 LA150 LA150 LA150 LA150 LA150 LA150 LA150 LA150 LA150 LA150

ENDF/B-VI I ENDF/B-VI I ENDF/B-VI I ENDF/B-VI I JENDL-HE

ENDF/B-VI I JEFF-31

ENDF/B-VI I ENDF/B-VI I

JEFF-31 JEFF-31

ENDF/B-VI I ENDF/B-VI I ENDF/B-VI I ENDF/B-VI I ENDF/B-VI I ENDF/B-VI I ENDF/B-VI I ENDF/B-VI I ENDF/B-VI I

The major isotopes in heavy concrete wall are O-16 (55 at%), Fe-56 (21 at%), H-1 (8 at%) and Ca-40 (5 at%)



10-6 10-5 10-4 10-3 10-2 10-1 100 101 102

109

1010

1011

1012

1013

1014

1015

1016

1017

1018

IFMIF MTC-9 model (mdl57, Nov 2011)(w/ graphite in LFTM)40 MeV 250 mA

Ne

utr

on

flu

x (/

cm2/M

eV

/s)

Neutron energy (MeV)

Back Plate HFTM UTM TRTM LFTM Vessel Liner (front)

Neutron spectra in Target Back Plate, HFTM, CFTM, TRTM,LFTM and in vessel liner

LFTM surrounded by graphite reflector



DPA (1/fpy)

1 2 3 4 5 6 7 80

5

10

15

20

25

30

35

40

row 1

row 2

row 3

Column no.

DP

A (

/fp

y)

1 2 3 4 5 6 7 8 : Column

Row

: 1

2

3DPA distribution (horizontal) in HFTM



Rigs region

DPA (/fpy)

DPA distribution (vertical) in HFTM



-29.75 -29.25

-28.75 -28.25

-27.75 -27.25

-26.75 -26.25

-25.75 -25.25

-24.75 -24.25

-23.75 -23.25

-22.75 -22.25

-21.75 -21.25

-20.75 -20.25

1 2 3 4 5 6 7 8 : Column

Row

: 1

2

3

1 2 3 4 5 6 7 80

2

4

6

8

10

12

14

row 1

row 2

row 3

Column no.

He

/DP

A

He/DPA distribution (vertical) in HFTM



Back plate HFTM CFTM TRTM LFTM10000000000000

100000000000000

1000000000000000

1.2E+15

5.3E+14

3.1E+14

1.0E+14

5.4E+13

FENDL-3/SLIBR2IFMIF std.

Neu

tro

n fl

ux

(/cm

^2/s

)

Back plate HFTM CFTM TRTM LFTM0.1

1

10

100

44.5

16.4

8.8

1.5

0.5

FENDL-3/SLIBR2IFMIF std.

DP

A(/

fpy

)

Þ No significant differences in the calculated neutron fluxes in the Test MdoulesÞ Differences of DPA accumulation is due to the 56Fe(n,dpa) cross section.

Total neutron fluxes and DPA accumulation in Back Plate and Test Modules: FENDL-3/SLIB-R2 vs. IFMIF Standard Library



Comparison of 56Fe displacement damage cross-sections

IFMIF-standard (LA150)

FENDL-3, release 2 (JEFF-3.1)

ENDF/B-VII.0

FENDL-3, release 3 (JEFF-3.1.1)

56Fe(n,dpa) (MT=444)1

10-1

10-2

10-3

10-3 10-2 10-1 1 10 102

Neutron energy (MeV)

Cro

ss s

ectio

n (b

arn)



1 2 3 4

-20%

-10%

0%

10%

20%

30%

40%

50%

n-flux

n-heating

DPA

p-prod

d-prod

t-prod

He-prod

p-flux

p-heating

Re

lati

ve

dif

fere

nc

e(F

3R

2-s

td)/

F3

R2

d-beam

Þ Relative differences are almost the same in all HFTM irradiation rigsÞ No differences in neutron fluxes Þ Large differences in DPA, T and He production

1 2 3 4

Comparison of nuclear responses in HFTM irradiation rigs




FENDL-3, release 2 (JEFF-3.1)

ENDF/B-VII.0

56Fe(n,xt) (MT=205)


FENDL-3, release 2 (JEFF-3.1)ENDF/B-VII.0

FENDL-3, release 3 (JEFF-3.1.1)

56Fe(n,xa) (MT=207)

1

10-1

10-2

10-3

Cro

ss s

ectio

n (b

arn)

1

10-1

10-2

10-3

0 10 20 30 40 50 60Neutron energy (MeV)

0 10 20 30 40 50 60Neutron energy (MeV)

Comparison of T - and He - production cross-sections of 56Fe



He production cross-section of Fe (nat)



Impact of of (n,xa) cross section of 56Fe

He/dpa ratio is one of the most important quantities for the material behaviour under irradiation

1 2 3 4 5 6 7 80

2

4

6

8

10

12

14

16

row 1

row 2

row 3

Column no.

He

/DP

A

1 2 3 4 5 6 7 80

2

4

6

8

10

12

14

16

row 1

row 2

row 3

Column no.

He

/DP

A

He/dpa calculated with (n,xa) cross section inFENDL-3/SLIB2 *

He/dpa calculated with (n,xa) cross section of ENDF/B-VII.0 *

Difference of the He production is 12 – 15%

* Using dpa cross section in LA150.



0 50 100 150 200 250 300 350 4001.00E-02

1.00E+00

1.00E+02

1.00E+04

1.00E+06

1.00E+08

1.00E+10

1.00E+12

Case a (IFMIF Std.)

Case b (FENDL-3/SLIB2)

Case c (H: LA150, Li: INPE, others: F3R2)

Case d (H:F3R3, Li: INPE, others: F3R2)

Distance from inner surface of front wall (cm)

Ne

utr

on

flu

x (

/cm

^2

/s)

Front wall : heavy concrete (density: 3.6 g/cc, thickness: 390 cm)

IFMIF shielding calculations: neutron flux profile across Test Cell front wall



320 330 340 350 360 370 380 3900.00E+00

2.00E+00

4.00E+00

6.00E+00

8.00E+00

1.00E+01

1.20E+01

1.40E+01

1.60E+01

1.80E+01

2.00E+01

Case a (IFMIF Std.)





Ne

utr

on

flu

x (

/cm

^2

/s)

IFMIF shielding calculations: neutron flux profile across Test Cell front wall (linear scale)



320 330 340 350 360 370 380 3900.00E+00

2.00E+00

4.00E+00

6.00E+00

8.00E+00

1.00E+01

1.20E+01

1.40E+01

1.60E+01

1.80E+01

2.00E+01

Case a (IFMIF Std.)





Bio

log

ica

l do

se

ra

te (

mic

roS

v/h

)

Due to H-1

Due to others (mainly O-16, Fe-56)

IFMIF shielding calculations: Profile of biological dose rate across Test Cell front wall (linear scale)



FENDL-3, Release 2 test library, successfully applied for full IFMIF neutronics calculations (TTC model with all materials included).FENDL-3, R2, ACE data library, with some modifications in routine use for IFMIF design and shielding analyses – it works. High energy extension for H-1 data essential for shielding calculations – works with new prepared for Release 3. Major concern is on the Fe-56 data in FENDL-3.

Still a matching problem at 20 MeV in the dpa cross section, which gives about 20 % smaller values than with LA150.There is a significant difference of the He-4 production cross section as compared to the measured data at LANCE/LANL (R. Haight et al.).

Summary


Documents

Application of the FENDL-3 Test Data Library to IFMIF