Abstract
Benchmark integral-experiment values from six fast critical-reactor assemblies and two standard neutron fields are combined with corresponding calculations using group cross sections based on ENDF/B-V in a least-squares data adjustment using evaluated covariances from ENDF/B-V and supporting covariance evaluations. The purpose is to produce an adjusted cross-section and covariance library which is based on well-documented data and methods and which is suitable for fast-reactor design. By use of such a library, data- and methods-related biases of calculated performance parameters should be reduced and uncertainties of the calculated values minimized. Consistency of the extensive data base is analyzed using the chi-square test. This adjusted library ORACLE will be available shortly. Feedback from designers, evaluators, experimentalists, and analysts is solicited.
| Original language | English |
|---|---|
| Title of host publication | Proceedings of the Conference, 1980 Advances in Reactor Physics and Shielding |
| Subtitle of host publication | September 14-17, 1980, Sun Valley, Idaho |
| Place of Publication | LaGrange Park, IL, USA |
| Publisher | American Nuclear Society |
| Pages | 705 - 19 |
| Number of pages | 14 |
| State | Published - 1980 |
Bibliographical note
ORACLE;adjusted cross-section;covariance library;fast-reactor analysis;critical-reactor assemblies;standard neutron fields;group cross sections;ENDF/B-V;Keywords
- fission reactor core control and monitoring
- fission reactor theory and design