NEUTRON CROSS SECTIONS FOR FAST AND INTERMEDIATE NUCLEAR REACTORS
Technical Report
·
OSTI ID:4277151
A neutron transport equation which was solved numerically has been connected with multigroup ncutron cross sections and critical assemblies to display the area of coverage and range of errors. The cross sections, critical assemblies, and results are tabulated. (auth)
- Research Organization:
- Los Alamos Scientific Lab., N. Mex.
- DOE Contract Number:
- W-7405-ENG-36
- NSA Number:
- NSA-13-009259
- OSTI ID:
- 4277151
- Report Number(s):
- LAMS-2255
- Country of Publication:
- United States
- Language:
- English
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