FUEL HANDLING MACHINE SHIELDING REQUIRMENTS FOR SRE CORE III
Technical Report
·
OSTI ID:4828681
Dose rates at various receiving points adjacent to the SRE fuel handling machine were calculated, assuming that the fuel element was exposed for a long time at peak power conditions in the SRE (PEP). It was further assumed that handling occurs 10 hours after reactor shutdown. Streaming underneath the fuel handling cask, whiIe the element is being raised into it, was considered not to be a problem, for if excessive, such a condition could be alleviated by means other than just adding to the thickness of the cask wall. The maximum allowable heat fiux of the SRE (PEP) design is set at 10/sup 6/ Btu/hr-ft/sup 2/ and calculations for obtaining source strengths were based on this number. Dose rates at each of the four points chosen were calculated for various thicknesses of lead and the results are summarized in graphs. From these figures it is clear, for example, that with an approximate equivalent thickness of 10'' of lead, as exists in the present fuel handling cask, the dose rate at point 1 will be 2097 mr/hr which is far above the allowable rate of 7.5 mr/hr (or 2.5 mr/hr average) for a 40 hour work week. If, for instance, the allowable dose rate is 2.5 mr/hr at the surface of the cask the thickness of lead required in the region of point 1 will be 15.1 in. Similarly, 12.4 in. is needed at point 2, 11.5 in. at point 3, and 10 in. at point 4. It is doubtful that the operator will ever be in contact with the cask at points 2, 3, and 4 and the shielding at these locations may be made somewhat thinner than suggested above (auth)
- Research Organization:
- Atomics International. Div. of North American Aviation, Inc., Canoga Park, Calif.
- DOE Contract Number:
- AT(11-1)-GEN-8
- NSA Number:
- NSA-16-024948
- OSTI ID:
- 4828681
- Report Number(s):
- NAA-SR-Memo-7212
- Country of Publication:
- United States
- Language:
- English
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