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).