NEUTRON AND GAMMA DOSE DISTRIBUTION BEYOND PRIMARY SHIELD MOCKUP NO. 2 (BERYLLIUM, SOLID IRON, WATER, AND SOLID IRON)
Technical Report
·
OSTI ID:4332969
Since the gamma attenuation of the first primary shield mockup was greater than required, a second mockup was tested which contained less iron. Also the B/sub 4/C layer was elinainated since it was a difficult material to handle in the shield and was not particularly advantageous at this location. The B/sub 4/C was initially present to reduce capture gamnaa production and radiation damage in the region requiring high-temperature shielding material, i.e., close to the reactor. It was found, however, that solid iron would suffice for this region and was preferred from the engineering point of view. (A.C.)
- Research Organization:
- Oak Ridge National Lab., Tenn.
- DOE Contract Number:
- W-7405-ENG-26
- NSA Number:
- NSA-12-008196
- OSTI ID:
- 4332969
- Report Number(s):
- CF-52-5-1(Pt.5)(Del.)
- Country of Publication:
- United States
- Language:
- English
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