Transcript Cross-section Covariance Data in JENDL-3.3

Review of Available Cross
Section Covariance Matrices
and their use in the scope of
reactor physics benchmarks
SG-26, 3 May 2006
1
Cross-section Covariance Data
in BROND-2.2
- File types are
• MF= 33 (cross sections)
- The Nuclides are:
• C-0, Au-197, Pb-0
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Cross-section Covariance Data
in CENDL-2.1
- File types are
• MF=31 (), 32 (resonances),
33 (cross sections), 34 (angular distributions)
- The Nuclides are:
• H-2, H-3, O-16, F-19, Mn-55, Fe-56,
U-235, U-238, Pu-240, Am-241
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Cross-section Covariance Data
in ENDF/B-VI.7
- File types are
• MF=31 (), 32 (resonances),
33 (cross sections)
- The Nuclides are:
• Li-7, C-0, F-19, Na-23, Si-0, Si-28, Si-29, Si-30,
Ti-46, Ti-47, Ti-48, V-0, Cr-50, Cr-52, Cr-53, Cr-54,
Mn-55, Fe-54, Fe-56, Fe-57, Fe-58, Co-59, Ni-58, Ni60, Ni-61, Ni-62, Ni-64, Cu-63, Cu-65, Y-89,
Nb-93, In-0, In-115, Re-185, Re-187, Au-197,
Pb-206, Pb-207, Pb-208, Bi-209, Th-232, U-235,
U-238, Pu-240, Pu-242, Am-241
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Cross-section Covariance Data in
ENDF/B-V
- File types are
• MF=31 (), 32 (resonances),
33 (cross sections),
- The Nuclides are:
• H-1, Li-6, Li-7, Be-9, B-10, C-0, N-14, O-16, F-19,
Na-23, Al-27, Si-0, Sc-45, Ti-46, Ti-47, Ti-48, Cr-0,
Mn-55, Fe-0, Fe-54, Fe-56, Fe-58, Co-59, Ni-0, Ni60, Cu-63, Cu-65, In-115, I-127, Au-197, Pb-0, Th232, U-235, U-238, Np-237, Pu-239, Pu-240, Pu241, Am-241.
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Cross-section Covariance Data
in JEFF-3.0
- File types are
• MF=31 (), 33 (cross sections),
34 (angular distributions)
- The Nuclides are:
• H-3, C-0, F-19, Si-28, V-0, Cr-50, Cr-53, Cr-54
Mn-55, Fe-54, Co-59, Ni-58, Ni-60, Ni-61,
Ni-62, Ni-64, Cu-63, Cu-65, Y-89, Nb-93,
Re-185, Re-187, Au-197, Bi-209, Th-232, U-238
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Cross-section Covariance Data
in JEF-2.2
- File types are
• MF=31 (), 33 (cross sections)
- The Nuclides are:
• H-1, Li-6, Li-7, Be-9, C-0, Co-59, Ni-58, Ni-60,
Ni-61, Ni-62, Ni-64, Y-89, Au-197, U-235, U-238
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Cross-section Covariance Data
in EFF-2.4
- File types are
• MF= 33 (cross sections), 34 (angular
distributions)
- The Nuclides are:
• H-1, Li-6, C-0, F-19, Al-27, V-0, Cr-52, Mn-55,
Fe-56, Co-59, Ni-58, Ni-60, Ni-61, Ni-62, Ni-64,
Cu-63, Cu-65, Nb-93, Re-185, Re-187
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Cross-section Covariance Data
in JENDL-3.3
- File types are
• MF=31 (), 32 (resonances),
33 (cross sections),34 (angular distributions) &
35 (spectra)
- The Nuclides are:
• H-1, B-10, B-11, O-16, Na-23, Ti-48, V-0,
Cr-52, Mn-55, Fe-56, Co-59, Ni-58, Ni-60,
Zr-90, U-233, U-235, U-238, Pu-239, Pu-240,
Pu-241
ERRORR-J module required for processing of some materials
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Processed Multigroup Covariance
Data Libraries
• ZZ-COVFILS: 30-Group Neutron Cross-Section Covariance
Library from ENDF/B-V (in BOXER format)
• ZZ-COVFILS-2: 74-Group Covariances for Fusion
Reactors, (ENDF/B-V)
• PUFF-2: Multigroup Covariance Matrices from ENDF/B-V &
processing code (COVERX Format)
• ZZ-DOSCOV: 24-Group Covariance Data Library from
ENDF/B-V for Dosimetry Calculation
• ZZ-COVERV: Multigroup Cross-Section Covariance
Matrices from ENDF/B-V
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Processed Multigroup Covariance
Data Libraries (cont.)
• ZZ-VITAMIN J/COVA: Covariance Matrix Data
Library based on JEF-1, ENDF/B-IV and -V data;
processing & verification codes
• ZZ-VITA.-J/COVA/EFF2: EFF-2.3 covariance
matrices for 18 materials, detector response function
covariances from IRDF 90.2
• ZZ-VITAMIN-J/COVA/EFF3: EFF-3 covariance
matrices for 5 materials: Be-9, Si-28, Fe-56, Ni-58,
Ni-60;
processing and verification utilities
• ERROR-J: processing code & JENDL-3.2, -3.3
covariance matrices
SG-26, 3 May 2006
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EFF-3 Covariance Matrix Library
Content of the library:
•
EFF-3 covariance matrices: Be-9, Si-28, Ni-58, Ni-60, Fe-56
- provided in BOXER format
- energy group structure as in evaluated files
- only File-33 data included
•
ANGELO-2 code for interpolation of covariance matrices to user defined
energy group structure; only file-33 covariance matrices can be treated
•
LAMBDA code for verification of mathematical properties of covariance
matrices
•
Reports with plots and lists of eigenvalues of all File 33 & 34 covariances
SG-26, 3 May 2006
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Be-9 covariance matrix processing with ANGELO
and NJOY codes
ANGELO (from BOXER library)
NJOY (from evaluated data files)
SG-26, 3 May 2006
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NEA-1730: ZZ-COV-15GROUPCovariance Data Review
Processing of available covariance data into 15 energy groups
for intercomparison and use (GEN-IV, ADS)
- NEA, FzK, ANL (M. Salvatores, G. Palmiotti)
ENDF/B-V: H-1, Li-6, B-10, C-12, N-14, O-16, Pb
EFF-3: Be-9, Fe-56, Ni-58, Si-28
IRDF-2002: Li-6(n,t), B-10(n,a), F-19(n,2n), Al-27(n,a), Fe56(n,p), Ni-58(n,2n)&(n,p), Zr-90(n,2n), Th-232(n,f)&(n,g), U235(n,f), U-238(n,f)&(n,g), Np-237(n,f), Pu-239(n,f), Am-241(n,f)
ENDF/B-VI.8: Li-7, F-19, Na-23, Si-0, Cr-52, Fe-56, Fe-57, Pb206, Pb-207, Pb-208, Bi-209, Th-232, U-235(nu-bar), U-238(nu-bar,
few inelastic levels), Pu-240
JENDL-3.3: Zr, U-233, U-238, Pu-239, Pu-241, Th-232
* in red – some problems persist
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IRPhE
International Reactor Physics
Experiments Database Project
NEA Secretary: E. Sartori
Chairman: J. Gadó
Technical review co-ordinator: B. Briggs
Project supervisors: P. D’hondt, A. Hasegawa, A. Zaetta
June 2003 mandate and work programme approved by NSC
IRPhE started officially since December 2003
Funds from the Government of Japan
http://www.nea.fr/html/dbprog/IRPhE-latest.htm
SG-26, 3 May 2006
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KRITZ-2 Benchmarks
 Transport calculation by THREEDANT and
TWODANT: input and JEF-2.2 cross-sections
provided by Winfried Zwermann, GRS (18 energy
groups, P-3, S-8)
 KRITZ 2.1, 2.13 and 2.19 cold & hot configurations
 SUSD3D sensitivity and uncertainty analysis using:
Direct and adjoint flux moments from THREE/TWO - DANT
partial cross-sections processed by NJOY/GROUPR
(thermal-1/e-fission+fusion weighting, several s0)
covariance matrices processed by NJOY/ERRORR and
NJOY/ERROR-J: ENDF/B-V, IRDF-90, JENDL-3.2, -3.3,
(JEF-2.2, JEFF-3.0)
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Kritz 2.1c: Uncertainties (in pcm)
based on various covariance data
800
700
600
500
Jendl3.3
400
ENDF/B-V
300
IRDF90.2
200
100
0
H
O
U5(n,f) U5(n,g) U5(nu) U8(n,f) U8(n,g) U8(nu)
SG-26, 3 May 2006
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Pu-239(n,f)
IRDF-90
JENDL-3.2
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SNEAK-7A&7B
-1
10
SNEAK
(n.f)
-2
- Relative sensitivity/ U
10
U-235 (7A)
U-238 (7A)
Pu-239 (7A)
U-235 (7B)
U-238 (7B)
Pu-239 (7B)
-3
10
-4
10
-5
10
-6
10
-7
10
-8
10
-3
10
-2
10
-1
10
0
10
1
10
2
10
3
10
4
10
5
10
6
10
7
10
Energy (eV)
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SNEAK-7A&7B
Relative sensitivity/ U
0.00
SNEAK
(n.gamma)
-0.02
-0.04
U-238 (7A)
Pu-239 (7A)
U-238 (7B)
Pu-239 (7B)
-0.06
-0.08
1
10
2
10
3
10
4
10
5
10
6
10
7
10
Energy (eV)
SG-26, 3 May 2006
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Fe-56(n,el)
EFF-3.1
JENDL-3.2
SG-26, 3 May 2006
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Fe-56(n,inel)
EFF-3.1
JENDL-3.2
SG-26, 3 May 2006
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GANDR - Sensitivity-Based Global Assessment of
Nuclear Data Requirements
• Project of the IAEA Nuclear Data Section (D. W. Muir)
• Tool for evaluating the potential contribution of a new
experiment for improving precision of basic nuclear
data. This aims at facilitating the choice between different
nuclear data measurement proposals.
• It is based in sensitivity and uncertainty analysis
methods
• A global evaluation of covariance matrices is necessary
taking into account the complete information available
on the nuclear data, including both differential and
integral data (ZOTTVL).
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