Preliminary Results of Nuclear Data S&U
Analysis for Benchmark Exercises
Using DANTSYS/SUSD3D
Sang-Ji KIM, Do Heon KIM, Choong-Sup GIL
Korea Atomic Energy Research Institute
6th Meeting of WPEC Subgroup 33 on “Methods and Issues for the
Combined Use of Integral Experiments and Covariance Data”
December 1, 2011
NEA, Issy-les-Moulineaux, FRANCE
- 2 -
I. Introduction
II. Preliminary Benchmark Results
III. Summary
CONTENTS
- 3 -
Preparation of Cross Section Data
Source ENDF
ENDF/B-VII.0
JENDL-4.0
NJOY99 Code Processing
Same NJOY processing options as KAFAX-libraries
(NEA-1815, -1816, -1817) except for energy group
structure (150 groups)
MATXS-format
Energy group structure: 33 groups of SG33 standard
Weighting function: KALIMER-150 core spectrum
I. Introduction
- 4 -
Preparation of Covariance Data
Source Covariance Data
JENDL-4.0
NJOY99 Code Processing
COVFIL-format
Energy group structure: 33 groups of SG33 standard
Nuclides included
Non-Actinides: B-10, B-11, O-16, Na-23, Mn-55, Fe-56,
Co-59, Ni-58, Ni-60
Actinides: U-234, U-235, U-238, Pu-238, Pu-239, Pu-
240, Pu-241, Pu-242, Am-241
- 5 -
Sn Transport Calculation by DANTSYS
Geometry
1-D Sphere model: JEZEBEL-Pu239, JEZEBEL-
Pu240, FLATTOP-Pu
2-D Cylinder (R-Z) model: ZPR-6/7, ZPR-6/7 High-
Pu240, JOYO Mk-I
Angular Quadrature Sets
S16, S8, S4: Traditional built-in Pn constants given by
DANTSYS (IQUAD=1)
S4: Quadrature set of SG33 standard (just for 1-D
calculations)
- 6 -
S&U Analysis by SUSD3D
DANTSYS
(33g)
*, GENDF
(33g)
COVFIL
(33g)
SUSD3D
JENDL-4.0
NJOY
TRANSX
ISOTXS(33g)
NJOY
(ERRORR)
- 7 -
II. Preliminary Benchmark Results
This Study
Benchmark calculations have been carried out for 7
benchmark exercises of WPEC SG33.
Validation of Integral Parameters
k-eff, spectral indices, Na void reactivities (ZPPR-9)
DANTSYS calculations
• ENDF/B-VII.0- and JENDL-4.0-based MATXS-format libraries
• Options: P1-S4, P1-S8 (JEZEBEL-Pu239, ZPR-6/7), P3-S16
• Same meshing and isotopic compositions as SG33 standard
• Different angular quadrature sets (S4) from SG33 standard
Corrective Factors for homogeneous deterministic
calculations (P1-S4, 33 groups)
- 8 -
This Study
Calculation of Nuclear Data Uncertainties to k-eff
Forward & Adjoint Fluxes: ENDF/B-VII.0 vs. JENDL-4.0
Same Covariance Data of JENDL-4.0 for both ENDF/B-
VII.0- and JENDL-4.0-based DANTSYS runs
Considering
• all nuclides with covariance data
• all nuclear reactions of covariance file
• inelastic scattering reactions with all discrete levels (MT=51-91,
not MT=4)
• normalized to sum of total nu sensitivities (MT=452) for all
actinides
- 9 -
Results with ENDF/B-VII.0-Based Library
No. Core Parameter Experiment
ENDF/B-VII.0
(P1-S4, Quad. Set of DANTSYS)
ENDF/B-VII.0
(P1-S4, Quad. Set of SG33)
C/E Uncertainty(%) C/E Uncertainty(%)
1
JEZEBEL-Pu239
keff 1.00000 1.003 0.48762 1.003 0.48809
2 F28/F25 0.2133 0.984 0.984
3 F49/F25 1.4609 0.980 0.980
4 F37/F25 0.9835 0.974 0.974
5 JEZEBEL-Pu240 keff 1.00000 1.003 0.43217 1.003 0.43228
6
FLATTOP-Pu
keff 1.00000 1.010 0.48961 1.010 0.49039
7 F28/F25 0.1799 0.987 0.987
8 F37/F25 0.8561 0.986 0.985
9
ZPR-6/7
keff 1.00051 1.001 1.20620
10 F28/F25 0.0223 0.988
11 F49/F25 0.9435 1.013
12 C28/F25 0.1323 1.024
13 ZPR-6/7 High-Pu240 keff 1.00080 1.000 1.18180
14
ZPPR-9
keff 1.00080 1.001 1.34660
15 F28/F25 0.0207 0.991
16 F49/F25 0.9225 0.989
17 C28/F25 0.1296 1.027
18 Na void (Step 3), pcm 106.0000 1.048
19 Na void (Step 5), pcm 109.0000 1.075
20 JOYO Mk-I keff 1.00105 1.005 0.84874
NOTE:
failed to apply 2D
quadrature set of
SG33 standard
might be
inadequate for
DANTSYS run
- 10 -
Results with JENDL-4.0-Based Library
No. Core Parameter Experiment
JENDL-4.0
(P1-S4, Quad. Set of DANTSYS)
JENDL-4.0
(P1-S4, Quad. Set of SG33)
C/E Uncertainty(%) C/E Uncertainty(%)
1
JEZEBEL-Pu239
keff 1.00000 1.001 0.48642 1.002 0.48697
2 F28/F25 0.2133 0.973 0.973
3 F49/F25 1.4609 0.989 0.989
4 F37/F25 0.9835 0.965 0.965
5 JEZEBEL-Pu240 keff 1.00000 1.001 0.43031 1.002 0.43048
6
FLATTOP-Pu
keff 1.00000 1.006 0.48943 1.007 0.49027
7 F28/F25 0.1799 0.983 0.983
8 F37/F25 0.8561 0.983 0.983
9
ZPR-6/7
keff 1.00051 1.005 1.18440
10 F28/F25 0.0223 0.992
11 F49/F25 0.9435 1.027
12 C28/F25 0.1323 1.031
13 ZPR-6/7 High-Pu240 keff 1.00080 1.004 1.16110
14
ZPPR-9
keff 1.00080 1.006 1.32050
15 F28/F25 0.0207 0.997
16 F49/F25 0.9225 1.003
17 C28/F25 0.1296 1.033
18 Na void (Step 3), pcm 106.0000 1.117
19 Na void (Step 5), pcm 109.0000 1.151
20 JOYO Mk-I keff 1.00105 1.007 0.84486
- 11 -
Comparison of Criticality Results
JEZEBEL-Pu239
JEZEBEL-Pu240
FLATTOP-Pu
ZPR-6/7
ZPR-6/7 High-Pu240
ZPPR-9
JOYO Mk-I
0.985
0.990
0.995
1.000
1.005
1.010
1.015
JENDL-4.0
P1-S4
P3-S16
C
/E V
alu
es o
f k
eff
ENDF/B-VII.0
P1-S4
P3-S16
Criticality
ENDF/B-VII.0 vs. JENDL-4.0
ENDF/B-VII.0
tend to be larger
than JENDL-4.0
for 1-D models
tend to be smaller
than JENDL-4.0
for 2-D models
- 12 -
Comparison of Integral Parameters
ENDF/B-VII.0 vs. JENDL-4.0
keff
F28/F25
F49/F25
F37/F25
0.96
0.97
0.98
0.99
1.00
1.01
JENDL-4.0
P1-S4
P1-S8
P3-S16
C/E
Va
lue
s o
f P
ara
me
ters
ENDF/B-VII.0
P1-S4
P1-S8
P3-S16
JEZEBEL-Pu239
keff
F28/F25
F37/F25
0.980
0.985
0.990
0.995
1.000
1.005
1.010
1.015
JENDL-4.0
P1-S4
P3-S16
C/E
Va
lue
s o
f P
ara
me
ters
ENDF/B-VII.0
P1-S4
P3-S16
FLATTOP-Pu
keff
F28/F25
F49/F25
C28/F25
0.98
0.99
1.00
1.01
1.02
1.03
1.04
JENDL-4.0
P1-S4
P1-S8
P3-S16
C/E
Va
lue
s o
f P
ara
me
ters
ENDF/B-VII.0
P1-S4
P1-S8
P3-S16
ZPR-6/7
keff
F28/F25
F49/F25
C28/F25
Na void(Step3)
Na void(Step5)
0.98
1.00
1.02
1.04
1.06
1.08
1.10
1.12
1.14
1.16
JENDL-4.0
P1-S4
P3-S16
C/E
Va
lue
s o
f P
ara
me
ters
ENDF/B-VII.0
P1-S4
P3-S16
ZPPR-9
Na Void Reactivity
tend to be
overestimated for
JENDL-4.0
- 13 -
Comparison of Total Uncertainty
ENDF/B-VII.0 vs. JENDL-4.0
JEZEBEL-Pu239
JEZEBEL-Pu240
FLATTOP-Pu
ZPR-6/7
ZPR-6/7 High-Pu240
ZPPR-9
JOYO Mk-I
0.0
0.2
0.4
0.6
0.8
1.0
1.2
1.4
1.6Total Uncertainty (%) due to JENDL-4.0 Covariance Data
T
ota
l U
nce
rta
inty
(%
) o
f k
eff
ENDF/B-VII.0
P1-S4
P3-S16
JENDL-4.0
P1-S4
P3-S16
Uncert. for P1-S4
tend to become
smaller than P3-
S16 for 1-D
models
due to changes in
elastic & inelastic
scattering
contributions
- 14 -
Uncertainty Contribution by Nuclides & Reactions
JEZEBEL-Pu239
Pu-239Pu-240
Pu-241
0.0
0.1
0.2
0.3
0.4
0.5
0.6JEZEBEL-Pu239
To
tal U
nce
rta
inty
(%
) b
y N
uclid
es
ENDF/B-VII.0
P1-S4
P1-S8
P3-S16
nelasn2n
nftot
ninel ngnutot
0.0
0.1
0.2
0.3
0.4
JEZEBEL-Pu239
To
tal U
nce
rta
inty
(%
) b
y P
u-2
39
Re
actio
ns
ENDF/B-VII.0
P1-S4
P1-S8
P3-S16
< by Nuclides > < by Reactions of Pu-239 >
- 15 -
Uncertainty Contribution by Nuclides & Reactions
ZPR-6/7
< by Nuclides >
O-1
6
Na-
23
Mn-
55
Fe-56
Co-
59
Ni-5
8
Ni-6
0
U-2
35
U-2
38
Pu-
238
Pu-
239
Pu-
240
Pu-
241
Pu-
242
Am
-241
0.0
0.1
0.2
0.3
0.4
0.5
0.6
0.7
0.8
0.9
1.0
1.1ZPR-6/7
To
tal U
nce
rta
inty
(%
) b
y N
uclid
es ENDF/B-VII.0
P1-S4
P1-S8
P3-S16
P1-S4 vs. P3-S16
elastic & inelastic
scattering
contributions
become negligible
for 2-D models.
- 16 -
< by Reactions of Pu-239 >
nelasn2n
nftot
ninel ngnutot
0.0
0.1
0.2
0.3
0.4
0.5
0.6
0.7
0.8
0.9
1.0ZPR-6/7
To
tal U
nce
rta
inty
(%
) b
y U
-23
8 R
ea
ctio
ns
ENDF/B-VII.0
P1-S4
P1-S8
P3-S16
nelasn2n
nftot
ninel ngnutot
0.00
0.05
0.10
0.15
0.20
0.25
0.30
0.35ZPR-6/7
To
tal U
nce
rta
inty
(%
) b
y P
u-2
39
Re
actio
ns
ENDF/B-VII.0
P1-S4
P1-S8
P3-S16
nelasn2n
ninel ng np na
0.00
0.05
0.10
0.15
0.20
ZPR-6/7
To
tal U
nce
rta
inty
(%
) b
y F
e-5
6 R
ea
ctio
ns
ENDF/B-VII.0
P1-S4
P1-S8
P3-S16
nelasn2n
ninel ng np na
0.00
0.03
0.06
0.09
0.12
0.15ZPR-6/7
To
tal U
nce
rta
inty
(%
) b
y N
a-2
3 R
ea
ctio
ns
ENDF/B-VII.0
P1-S4
P1-S8
P3-S16
< by Reactions of U-238 >
< by Reactions of Na-23 > < by Reactions of Fe-56 >
- 17 -
Work flow of V&V activity
Status of V&V Activity at KAERI
Open DB
(IRPhE, CSEWG)
ZPPR-15
(I-NERI, on going)
IPPE BFS DB
(ISTC, under
discussion)
TRU burner physics
experiment
(New, BFS-76-1)
BFS experiment
(73, 75, 55)
Assessment of
applicability
Reactor physics
experiment DB
Sensitivity coeff.,
(APSTRACT)
NJOY (ERROR)
or engineering
decision
Covariance Data
Data Library
(ENDF/B, JEFF,
JENDL)
Cross Section
Adjustment
(ATCROSS)
Adjusted LibraryAssessment of
adjusted library
Completed
On going
Plan
- 18 -
Development of sensitivity analysis
code (APSTRACT)
Using perturbation theory based SN
transport theory
Forward and adjoint flux from
TWODANT calculation
Using self-shielded cross section in
ISOTXS
Status of V&V Activity at KAERI
10-2
10-1
100
101
102
103
104
105
106
107
108
-0.002
0.000
0.002
0.004
0.006
0.008
0.010
0.012
0.014
0.016
0.018
-100
0
100
200
300
400
500
600
700
Reference
ZPR-3-48
ZPR-9
ZPR-3-56B
ZEBRA-MZA
Se
nsitiv
ity to
k-e
ffe
ctive
Neutron energy [eV]
Pu-239 fission to k-effective
Diffe
ren
ce
[%
]
< Comparison of integral sensitivity coefficients of reactor physics exp.
with reference core1)>
Ref. 1) ZPR-3-48 ZPR-6-6A ZPR-9 ZPR-3-56B ZEBRA-MZA
Pu239 Fission 0.4382 0.5739 - 0.5659 0.5913 0.5569
Nu 0.6192 0.8219 - 0.7859 0.8581 0.7830
Capture -0.0355 -0.0641 - -0.0517 -0.0714 -0.0478
U238 Fission 0.0574 0.0849 0.0726 0.0953 0.0652 0.0624
Nu 0.0981 0.1454 0.1198 0.1599 0.1065 0.1033
Capture -0.1509 -0.2051 -0.2667 -0.2302 -0.1638 -0.1292
PU241 Fission 0.0419 0.0094 - 0.0173 0.0187 0.0370
Nu 0.0627 0.0138 - 0.0251 0.0276 0.0531
Capture -0.0167 -0.0043 - -0.0072 -0.0102 -0.0123
Na Capture -0.0017 -0.0008 -0.0021 -0.0012 -0.0019 -0.0008
Fe Capture -0.0196 -0.0070 -0.0175 -0.0081 -0.0141 -0.0078
Sensitivity coeff. of Pu-239 fission to k-eff
1) Reference core represents the
TRU burner core for which BFS-
76-1 experiment was performed
- 19 -
Development of cross section adjustment technology
Major Topics of Research
Requirement of cross section adjustment
Determination of target accuracy and selection of reactor physics experiment from
open documents
Methodology of adjustment
Generalized least square method
Development of XS adjustment code (ATCROSS)
Interface with sensitivity analysis code
Interface with NJOY code for covariance (COVFILS format)
Uncertainty analysis and
representativeness analysis
Major Achievements and
Further Utilization
Requirement of cross section adjustment
Selection of applicable physics experiment
DB from open database
Cross section adjustment code (ATCROSS)
Utilization for producing adjusted
multi-group library
Status of V&V Activity at KAERI
APSTRACT (‘09)
(Sensitivity analysis)
Perturbation integral
(‘09) (PTBINT)
Sensitivity coeff. (‘09)
(SENSCF)
Adjustment code(‘10)
(ATCROSS)
Adjusted multi-group library (‘11)
Uncertainty and
representativeness analysis (‘10)
NJOY99 (‘11)
(Covariance matrix)
Interface module for
covariance(‘10) (COVFILS)
- 20 -
First contribution to WPEC SG33 by KAERI
Generation of MATXS-format cross section libraries based
on ENDF/B-VII.0 and JENDL-4.0
Generation of COVFIL-format covariance libraries based on
JENDL-4.0
Calculation of integral parameters for 7 benchmark
exercises of WPEC SG33
Estimation of nuclear data uncertainties to k-eff
Future Works
Estimate nuclear data uncertainties to remaining integral
parameters (spectral indices, Na void reactivities)
Apply COMMARA-2.0 or ENDF/B-VII.1 covariance data
Nuclear data adjustment
III. Summary
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