239Pu evaluation comparison study

Abstract The analysis of 239Pu was performed using the SAMMY Code for Neutron Transmission, Capture, and Fission cross-sections in the resolved resonance region up to 2.5 keV. Due to the difficulties of processing large covariance matrices, the evaluations were performed in the following distinct uncorrelated energy regions: 0.0–1.0 keV, 1.0 keV–2.0 keV, and 2.0 keV–2.5 keV. By using version 8.0.0 of the SAMMY code, the treatment of large resonance parameter covariance matrices was improved significantly. The aim of this work is to analyze the experimental data using a self-developed experimental nuclear data fitting code FITWR and analyze it with the SAMMY code, then compare the results with Bayes method. Finally, the output results from these methods is processed by the SAMMY code in order to obtain covariance matrix resonance parameters in the energy range from 0 to 2.5 keV. All the computational experiments done for this paper was carried out at IMAN1 Center – Jordan’s National Supercomputing Center (IMAN1).

[1]  Said F. Mughabghab,et al.  Atlas of neutron resonances , 2018 .

[2]  Mohammad Alrwashdeh,et al.  233U Evaluation Comparison Study , 2014 .

[3]  H. Weaver,et al.  Measurement of the Neutron Capture and Fission Cross Sections of 239Pu and 235U, 0.02 eV to 200 keV, the Neutron Capture Cross Sections of 197Au, 10 to 50 keV, and Neutron Fission Cross Sections of 233U, 5 to 20 , 1976 .

[4]  R. W. Hockenbury,et al.  Simultaneous Measurement of the Neutron Fission and Absorption Cross Sections of Plutonium-239 Over the Energy Region 0.02 eV to 30 keV , 1971 .

[5]  L. W. Weston,et al.  Normalization and Minimum Values of the 239Pu Fission Cross Section , 1993 .

[6]  Wang Kan,et al.  U233 Data Evaluation for Criticality Study , 2016 .

[7]  Jian Yu,et al.  Nuclear Data Statistical Treatment , 2013 .

[8]  M. Alrwashdeh Covariance data evaluation for 233U. , 2017, Applied radiation and isotopes : including data, instrumentation and methods for use in agriculture, industry and medicine.

[9]  Wang Kan,et al.  Development of a code FITWR for nuclear cross section statistical analysis , 2014 .

[10]  J. H. Todd,et al.  Measurements of the Neutron Fission Cross Sections of 235 U ( E n = 0.01 eV to 30 keV) and 239 Pu ( E n = 0.01 to 60 eV) , 1984 .

[11]  J. H. Todd,et al.  Subthreshold Fission Cross Section of 240 Pu and the Fission Cross Sections of 235 U and 239 Pu , 1984 .

[12]  J. H. Todd,et al.  HIGH-RESOLUTION FISSION CROSS-SECTION MEASUREMENTS OF 235U AND 239PU , 1992 .

[13]  P. V. Uffelen,et al.  NORMALIZATION OF THE 239PU FISSION CROSS SECTION , 1993 .