RADIAL THERMAL AND FAST NEUTRON FLUX DISTRIBUTIONS IN THE SODIUM REACTOR EXPERIMENT (SRE) AND IN THE TITLE I CONFIGURATION OF THE HALLAM NUCLEAR FACILITY (HNPF)
The thermal neutron flux distributions for the Sodium Reactor Experiment and the Hallam Power Reacter radial shields are calculated by three different methods. The method giving the highest fluxes is used to calculate conservative values of the heat generation rates in these shields. (T.F.H.)
- Research Organization:
- Atomics International. Div. of North American Aviation, Inc., Canoga Park, Calif.
- Sponsoring Organization:
- USDOE
- NSA Number:
- NSA-15-025640
- OSTI ID:
- 4014430
- Report Number(s):
- NAA-SR-Memo-3552
- Country of Publication:
- United States
- Language:
- English
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