Actions for NEUTRON AND GAMMA DOSE DISTRIBUTION BEYOND BERYLLIUM-SOLID IRON SHIELD IN WATER

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NEUTRON AND GAMMA DOSE DISTRIBUTION BEYOND BERYLLIUM-SOLID IRON SHIELD IN WATER

Author
Clifford, C. E.
Published
United States : [publisher not identified], 1952.
[Oak Ridge, Tennessee] : [U.S. Atomic Energy Commission], 1952.
Physical Description
microopaque : positive ; 8 x 13 cm

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Summary
The beryllium-- solid iron--water measurements were taken to aid in determining the feasibility of eliminating the boron carbide in the high- temperature regions of primary and top plug shields. A solid iron layer beyond the beryllium would become less effective as a gamma shield with increasing thickness because of the excessive production of capture gammas in and beyond the slab. This would tend to increase the over-all shield weight somewhat over that for the boron carbide shield. Measurements were taken of both the gamma and neutron dose distribution beyond the iron in the beryllium, iron, water configuration. The measurements of the gamma dose indicate the iron is quite effective for a thickness up to 20 cm. As the thickness increases beyond 20 cm the apparent relaxation length becomes very long and eventually becomes longer than that for water, which causes the dose at a fixed distance from the source to increase with replacement of water with iron. The neutron dosage measurements were taken to aid in estimating the relative transmitted dose and radiation damage beyond the solid iron as compared with that in the boron carbide design. (A.C.)
Report Numbers
CF-52-5-1(Pt.2)(Del.)
Other Subject(s)
Collection
U.S. Atomic Energy Commission depository collection.
Note
DOE contract number: W-7405-ENG-26
NSA number: NSA-12-008193
OSTI Identifier 4343464
Research organization: Oak Ridge National Lab., Tenn..
View MARC record | catkey: 39619256