application of the fendl-3 test data library to ifmif
DESCRIPTION
Application of the FENDL-3 Test Data Library to IFMIF. U. Fischer, K. Kondo, A . Serikov, P. Pereslavtsev. Overview. Test application of FENDL-3 neutron data library for IFMIF neutronics calculations - PowerPoint PPT PresentationTRANSCRIPT
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
33rd Research Coordination Meeting on FENDL-3, IAEA, Vienna, December 6 – 9, 2011
CAD Model of IFMIF Target and Test Cell (TTC) including vessel, Target assembly, concrete cover, Test Modules and pipes (2010)
U. Fischer, KIT, FENDL-3 Test Application to IFMIF
43rd Research Coordination Meeting on FENDL-3, IAEA, Vienna, December 6 – 9, 2011
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
U. Fischer, KIT, FENDL-3 Test Application to IFMIF
53rd Research Coordination Meeting on FENDL-3, IAEA, Vienna, December 6 – 9, 2011
250 cm
Access cell
Access/Maintenance Room
Access cell floor
Test cell ceiling
400 cm
Dedicated TTC model for IFMF shielding calculations
U. Fischer, KIT, FENDL-3 Test Application to IFMIF
63rd Research Coordination Meeting on FENDL-3, IAEA, Vienna, December 6 – 9, 2011
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)
U. Fischer, KIT, FENDL-3 Test Application to IFMIF
73rd Research Coordination Meeting on FENDL-3, IAEA, Vienna, December 6 – 9, 2011
8.1 cm
Beam footprint
Beam level
Specimen (Eurofer & NaK filling)
Heater (Eurofer & NiCr)
IFMIF TTC model: HFTM module front view (vertical cut)
U. Fischer, KIT, FENDL-3 Test Application to IFMIF
83rd Research Coordination Meeting on FENDL-3, IAEA, Vienna, December 6 – 9, 2011
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)
U. Fischer, KIT, FENDL-3 Test Application to IFMIF
93rd Research Coordination Meeting on FENDL-3, IAEA, Vienna, December 6 – 9, 2011
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%)
U. Fischer, KIT, FENDL-3 Test Application to IFMIF
103rd Research Coordination Meeting on FENDL-3, IAEA, Vienna, December 6 – 9, 2011
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
U. Fischer, KIT, FENDL-3 Test Application to IFMIF
113rd Research Coordination Meeting on FENDL-3, IAEA, Vienna, December 6 – 9, 2011
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
U. Fischer, KIT, FENDL-3 Test Application to IFMIF
123rd Research Coordination Meeting on FENDL-3, IAEA, Vienna, December 6 – 9, 2011
Rigs region
DPA (/fpy)
DPA distribution (vertical) in HFTM
U. Fischer, KIT, FENDL-3 Test Application to IFMIF
133rd Research Coordination Meeting on FENDL-3, IAEA, Vienna, December 6 – 9, 2011
-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
U. Fischer, KIT, FENDL-3 Test Application to IFMIF
143rd Research Coordination Meeting on FENDL-3, IAEA, Vienna, December 6 – 9, 2011
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
U. Fischer, KIT, FENDL-3 Test Application to IFMIF
153rd Research Coordination Meeting on FENDL-3, IAEA, Vienna, December 6 – 9, 2011
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)
U. Fischer, KIT, FENDL-3 Test Application to IFMIF
163rd Research Coordination Meeting on FENDL-3, IAEA, Vienna, December 6 – 9, 2011
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
U. Fischer, KIT, FENDL-3 Test Application to IFMIF
173rd Research Coordination Meeting on FENDL-3, IAEA, Vienna, December 6 – 9, 2011
IFMIF-standard (LA150)
FENDL-3, release 2 (JEFF-3.1)
ENDF/B-VII.0
56Fe(n,xt) (MT=205)
IFMIF-standard (LA150)
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
U. Fischer, KIT, FENDL-3 Test Application to IFMIF
183rd Research Coordination Meeting on FENDL-3, IAEA, Vienna, December 6 – 9, 2011
He production cross-section of Fe (nat)
U. Fischer, KIT, FENDL-3 Test Application to IFMIF
193rd Research Coordination Meeting on FENDL-3, IAEA, Vienna, December 6 – 9, 2011
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.
U. Fischer, KIT, FENDL-3 Test Application to IFMIF
203rd Research Coordination Meeting on FENDL-3, IAEA, Vienna, December 6 – 9, 2011
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
U. Fischer, KIT, FENDL-3 Test Application to IFMIF
213rd Research Coordination Meeting on FENDL-3, IAEA, Vienna, December 6 – 9, 2011
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.)
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)
IFMIF shielding calculations: neutron flux profile across Test Cell front wall (linear scale)
U. Fischer, KIT, FENDL-3 Test Application to IFMIF
223rd Research Coordination Meeting on FENDL-3, IAEA, Vienna, December 6 – 9, 2011
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.)
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)
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)
U. Fischer, KIT, FENDL-3 Test Application to IFMIF
233rd Research Coordination Meeting on FENDL-3, IAEA, Vienna, December 6 – 9, 2011
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
U. Fischer, KIT, FENDL-3 Test Application to IFMIF