PHYSICS OF INTERMEDIATE REACTORS
Technical Report
·
OSTI ID:4282808
The neutron diffusion approximation equations and multigroup averaged cross sections were correlated with a systematic transport approximation study of a wide spectrum of critical assemblies and the results tabulated. The small differences were corrected by neutron age considerations where significant with respect to experimental results. Initial results for temperature effects on reactivity of graphite reactors are indicated. (auth)
- Research Organization:
- Los Alamos Scientific Lab., N. Mex.
- DOE Contract Number:
- W-7405-ENG-36
- NSA Number:
- NSA-13-010634
- OSTI ID:
- 4282808
- Report Number(s):
- LAMS-2288
- Country of Publication:
- United States
- Language:
- English
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