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U.S. Department of Energy
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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