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Covariances Obtained from an Evaluation of the Neutron Cross Section Standards

Journal Article · · Nuclear Data Sheets
 [1];  [2];  [3];  [4];  [5];  [6];  [4];  [7];  [8];  [3];  [9]; ;  [10]
  1. Central Research Institute of Management, Economics and Information, Moscow (Russian Federation)
  2. Tsinghua University, Beijing (China)
  3. Institute of Physics and Power Engineering, Obninsk, Kaluga Region (Russian Federation)
  4. Los Alamos National Laboratory, Los Alamos, NM (United States)
  5. Institute for Reference Materials and Measurements, Geel (Belgium)
  6. Erlangen-Nuernberg University, Erlangen (Germany)
  7. Oak Ridge National Laboratory, Oak Ridge, TN (United States)
  8. Korea Atomic Energy Research Institute, Yuseong, Daejeon (Korea, Republic of)
  9. Argonne National Laboratory, Argonne, IL (United States)
  10. Vienna University, Vienna (Austria)
New measurements and an improved evaluation process were used to obtain a new evaluation of the neutron cross section standards. Efforts were made to include as much information as possible on the components of the data uncertainties that were then used to obtain the covariance matrices for the experimental data. Evaluations were produced from this process for the {sup 6}Li(n,t), {sup 10}B(n,{alpha}), {sup 10}B(n,{alpha}{sub 1}{gamma}), {sup 197}Au(n,{gamma}), {sup 235}U(n,f), and {sup 238}U(n,f) standard cross sections as well as the non-standard {sup 6}Li(n,n), {sup 10}B(n,n), {sup 238}U(n,{gamma}) and {sup 239}Pu(n,f) cross sections. There is a general increase in the cross sections for most of the new evaluations, by as much as about 5%, compared with the ENDF/B-VI results. Covariance data were obtained for the {sup 6}Li(n,t), {sup 6}Li(n,n), {sup 10}B(n,{alpha}), {sup 10}B(n,{alpha}{sub 1}{gamma}), {sup 10}B(n,n), {sup 197}Au(n,{gamma}), {sup 235}U(n,f), {sup 238}U(n,f), {sup 238}U(n,{gamma}) and {sup 239}Pu(n,f) reactions. Also an independent R-Matrix evaluation was produced for the H(n,n) standard cross-section, however, covariance data are not available for this reaction. The evaluations were used in the new ENDF/B-VII library.
OSTI ID:
21163777
Journal Information:
Nuclear Data Sheets, Journal Name: Nuclear Data Sheets Journal Issue: 12 Vol. 109; ISSN NDTSBA; ISSN 0090-3752
Country of Publication:
United States
Language:
English