sg-26, 3 may 20061 review of available cross section covariance matrices and their use in the scope...
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SG-26, 3 May 2006 1
Review of Available Cross Section Covariance Matrices and their use in the scope of reactor physics benchmarks
SG-26, 3 May 2006 2
Cross-section Covariance Data in BROND-2.2
- File types are • MF= 33 (cross sections)
- The Nuclides are: • C-0, Au-197, Pb-0
SG-26, 3 May 2006 3
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
SG-26, 3 May 2006 4
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, Ni-60, 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
SG-26, 3 May 2006 5
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, Ni-60, Cu-63, Cu-65, In-115, I-127, Au-197, Pb-0, Th-232, U-235, U-238, Np-237, Pu-239, Pu-240, Pu-241, Am-241.
SG-26, 3 May 2006 6
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
SG-26, 3 May 2006 7
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
SG-26, 3 May 2006 8
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
SG-26, 3 May 2006 9
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
SG-26, 3 May 2006 10
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
SG-26, 3 May 2006 11
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 12
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 13
Be-9 covariance matrix processing with ANGELO and NJOY codes
ANGELO (from BOXER library) NJOY (from evaluated data files)
SG-26, 3 May 2006 14
NEA-1730: ZZ-COV-15GROUP- Covariance 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, PbEFF-3: Be-9, Fe-56, Ni-58, Si-28IRDF-2002: Li-6(n,t), B-10(n,), F-19(n,2n), Al-27(n,a), Fe-56(n,p), Ni-58(n,2n)&(n,p), Zr-90(n,2n), Th-232(n,f)&(n,), U-235(n,f), U-238(n,f)&(n,), 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, Pb-206, Pb-207, Pb-208, Bi-209, Th-232, U-235(nu-bar), U-238(nu-bar, few inelastic levels), Pu-240JENDL-3.3: Zr, U-233, U-238, Pu-239, Pu-241, Th-232* in red – some problems persist
SG-26, 3 May 2006 15
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 16
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 ) 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)
SG-26, 3 May 2006 17
Kritz 2.1c: Uncertainties (in pcm) based on various covariance data
0
100
200
300
400
500
600
700
800
H O U5(n,f) U5(n,g) U5(nu) U8(n,f) U8(n,g) U8(nu)
J endl3.3
ENDF/B-V
IRDF90.2
SG-26, 3 May 2006 18
Pu-239(n,f)
IRDF-90 JENDL-3.2
SG-26, 3 May 2006 19
10-3
10-2
10-1
100
101
102
103
104
105
106
107
10-8
10-7
10-6
10-5
10-4
10-3
10-2
10-1
SNEAK(n.f)
U-235 (7A) U-238 (7A) Pu-239 (7A) U-235 (7B) U-238 (7B) Pu-239 (7B)
- R
elat
ive
sens
itivi
ty/
U
Energy (eV)
SNEAK-7A&7B
SG-26, 3 May 2006 20
101
102
103
104
105
106
107
-0.08
-0.06
-0.04
-0.02
0.00
SNEAK(n.gamma)
U-238 (7A) Pu-239 (7A) U-238 (7B) Pu-239 (7B)
Rel
ativ
e se
nsiti
vity
/ U
Energy (eV)
SNEAK-7A&7B
SG-26, 3 May 2006 21
Fe-56(n,el)
EFF-3.1 JENDL-3.2
SG-26, 3 May 2006 22
EFF-3.1 JENDL-3.2
Fe-56(n,inel)
SG-26, 3 May 2006 23
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).