Download presentation

Presentation is loading. Please wait.

Published byConner Hayn Modified over 3 years ago

1
SG-26, 3 May 20061 Review of Available Cross Section Covariance Matrices and their use in the scope of reactor physics benchmarks

2
SG-26, 3 May 20062 Cross-section Covariance Data in BROND-2.2 -File types are MF= 33 (cross sections) - The Nuclides are: C-0, Au-197, Pb-0

3
SG-26, 3 May 20063 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

4
SG-26, 3 May 20064 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

5
SG-26, 3 May 20065 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.

6
SG-26, 3 May 20066 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

7
SG-26, 3 May 20067 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

8
SG-26, 3 May 20068 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

9
SG-26, 3 May 20069 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

10
SG-26, 3 May 200610 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

11
SG-26, 3 May 200611 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

12
SG-26, 3 May 200612 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

13
SG-26, 3 May 200613 Be-9 covariance matrix processing with ANGELO and NJOY codes ANGELO (from BOXER library) NJOY (from evaluated data files)

14
SG-26, 3 May 200614 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, Pb EFF-3: Be-9, Fe-56, Ni-58, Si-28 IRDF-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-240 JENDL-3.3: Zr, U-233, U-238, Pu-239, Pu-241, Th-232 * in red – some problems persist

15
SG-26, 3 May 200615 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

16
SG-26, 3 May 200616 KRITZ-2 Benchmarks zTransport calculation by THREEDANT and TWODANT: input and JEF-2.2 cross-sections provided by Winfried Zwermann, GRS (18 energy groups, P-3, S-8) zKRITZ 2.1, 2.13 and 2.19 cold & hot configurations zSUSD3D sensitivity and uncertainty analysis using: yDirect and adjoint flux moments from THREE/TWO - DANT partial cross-sections processed by NJOY/GROUPR (thermal-1/e-fission+fusion weighting, several ) ycovariance 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)

17
SG-26, 3 May 200617 Kritz 2.1c: Uncertainties (in pcm) based on various covariance data

18
SG-26, 3 May 200618 Pu-239(n,f) IRDF-90JENDL-3.2

19
SG-26, 3 May 200619 SNEAK-7A&7B

20
SG-26, 3 May 200620 SNEAK-7A&7B

21
SG-26, 3 May 200621 Fe-56(n,el) EFF-3.1JENDL-3.2

22
SG-26, 3 May 200622 EFF-3.1JENDL-3.2 Fe-56(n,inel)

23
SG-26, 3 May 200623 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).

Similar presentations

Presentation is loading. Please wait....

OK

Regression with Panel Data

Regression with Panel Data

© 2017 SlidePlayer.com Inc.

All rights reserved.

Ads by Google

Ppt on model view controller mvc Download ppt on trigonometric functions for class 11 Ppt on javascript events trigger Ppt on bmc remedy 9 Download ppt on non conventional energy resources Ppt on synthesis and degradation of purines and pyrimidines are what Ppt on pir sensor based security system Ppt on class b power amplifier Ppt on new company act 2013 Ppt on material heritage of india