Covariance Matrices for Differential and Angle Integrated Neutron-Induced Elastic and Inelastic Scattering Cross Sections of 56Fe

被引：6

作者：

Chen, Shengli ^{[1
,2
]}

Bernard, David ^{[1
]}

Archier, Pascal ^{[1
]}

De Saint Jean, Cyrille ^{[1
]}

Noguere, Gilles ^{[1
]}

Tamagno, Pierre ^{[1
]}

机构：

[1] CEA, DEN DER SPRC LEPh, F-13108 St Paul Les Durance, France

[2] Univ Grenoble Alpes, I MEP2, F-38402 St Martin Dheres, France

来源：

5TH INTERNATIONAL WORKSHOP ON NUCLEAR DATA EVALUATION FOR REACTOR APPLICATIONS (WONDER-2018) | 2019年 / 211卷

关键词：

D O I：

10.1051/epjconf/201921107002

中图分类号：

O57 [原子核物理学、高能物理学];

学科分类号：

070202 ;

摘要：

Correlations between neutron inelastic scatterings angular distributions are not included in the Joint Evaluated Fission and Fusion (JEFF) nuclear data library, while they are key quantities for uncertainty propagation of nuclear data. By reproducing the angle-integrated cross sections and uncertainties of JEFF-3.1.1, the present work obtains covariance matrix between high energy model parameters using the least square method implemented in the CONRAD code. With this matrix, it is possible to generate correlations between angle-integrated cross sections and angular distributions, which are usually presented by Legendre coefficients. As expected, strong correlations are found, for example, between the Legendre coefficients of elastic and first-level-inelastic scatterings and the angle-integrated total, elastic, total inelastic cross sections.

引用

页数：7

共 14 条

[1] CONRAD Evaluation Code: Development Status and Perspectives
Archier, P.
De Saint Jean, C.
Litaize, O.
Noguere, G.
Berge, L.
Privas, E.
Tamagno, P.
[J]. NUCLEAR DATA SHEETS, 2014, 118 : 488 - 490
[2] RIPL - Reference Input Parameter Library for Calculation of Nuclear Reactions and Nuclear Data Evaluations
Capote, R.
Herman, M.
Oblozinsky, P.
Young, P. C.
Goriely, S.
Belgya, T.
Ignatyuk, A. V.
Koning, A. J.
Hilaire, S.
Plujko, V. A.
Avrigeanu, M.
Bersillon, O.
Chadwick, M. B.
Fukahori, T.
Ge, Zhigang
Han, Yinlu
Kailas, S.
Kopecky, J.
Maslov, V. M.
Reffo, G.
Sin, M.
Soukhovitskii, E. Sh.
Talou, P.
[J]. NUCLEAR DATA SHEETS, 2009, 110 (12) : 3107 - 3213
[3] Radial distributions of power and isotopic concentrations in candidate accident tolerant fuel U3Si2 and UO2/U3Si2 fuel pins with FeCrAl cladding
Chen, Shengli
Yuan, Cenxi
Guo, Daxi
[J]. ANNALS OF NUCLEAR ENERGY, 2019, 124 : 460 - 471
[4] Neutronic Analysis on Potential Accident Tolerant Fuel-Cladding Combination U3Si2-FeCrAl
Chen, Shengli
Yuan, Cenxi
[J]. SCIENCE AND TECHNOLOGY OF NUCLEAR INSTALLATIONS, 2017, 2017
[5] Clouvel L., 2018, PHYSOR 2018 CANC MEX
[6] Kinney W. E., 1976, International Conference on the Interactions of Neutrons with Nuclei
[7] TALYS-1.0
Koning, A. J.
Hilaire, S.
Duijvestijn, M. C.
[J]. INTERNATIONAL CONFERENCE ON NUCLEAR DATA FOR SCIENCE AND TECHNOLOGY, VOL 1, PROCEEDINGS, 2008, : 211 - +
[8] R-MATRIX THEORY OF NUCLEAR REACTIONS
LANE, AM
THOMAS, RG
[J]. REVIEWS OF MODERN PHYSICS, 1958, 30 (02) : 257 - 353
[9] Dispersive andglobal spherical optical model with a local energy approximation for the scattering of neutrons by nuclei from 1 keV to 200 MeV
Morillon, B
Romain, P
[J]. PHYSICAL REVIEW C, 2004, 70 (01): : 014601 - 1
[10] Zero Variance Penalty Model for the Generation of Covariance Matrices in Integral Data Assimilation Problems
Noguere, G.
Archier, P.
De Saint Jean, C.
Habert, B.
[J]. NUCLEAR SCIENCE AND ENGINEERING, 2012, 172 (02) : 164 - 179

← 1 2 →