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Title: Energy spectrum of leakage neutrons from a homogeneous reactor

Technical Report ·
OSTI ID:160888

The leakage neutron spectrum from a chain reaction in an aqueous solution of uranyl nitrate has been determined for the purpose of calibrating indium foil to be used for personnel monitoring of a possible accidental critical reaction at K-25. Approximately 75% of the neutrons were found to be slow, and experimental results are in reasonable agreement with a semi-theoretical treatment of the problem. The overall cross section of indium for neutrons of all energies in this leakage spectrum was found to be about 60 +/- 4 barns. This is of the same order of magnitude as the value of 126 barns which was determined from the calculated energy spectrum using weighted averages of directly measured cross sections.

Research Organization:
Union Carbide Nuclear Co., Oak Ridge, TN (United States)
OSTI ID:
160888
Report Number(s):
AD-A-297560/5/XAB; CNN: Contract W-7405-ENG-26; TRN: 53380574
Resource Relation:
Other Information: PBD: 5 Jul 1951
Country of Publication:
United States
Language:
English