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COMPUTING ABSOLUTE THERMAL NEUTRON FLUX FROM MEASUREMENTS MADE WITH INDIUM FOILS

Journal Article · · Nuclear Sci. and Eng.
OSTI ID:4302142

The method for computing absolute thermal neutron fiux from measurements made with activated indium foils is described, By combining data from the conuting rate of indium foils in 2 pi proportional counters with appropriate corrections for foil weights and neutron effects, the thermal flux is expressed in terms of sigma o, the thermal absorption cross section of In/sup 115/. This procedure may be used by laboratories which do not have access to a standard graphite pile or to a standard neutron source. This method has an estimated error less than 5% which is a function of the accuracy with which it is possible to determine the various correc tion factors for beta counting, A possible fixed erro in the value of sigma /sup 0 can easily be corrected for and incorporated into the methods used. (auth)

Research Organization:
Univ. of California, Los Angeles; North American Aviation, Inc., Canoga Park, Calif.
NSA Number:
NSA-13-001310
OSTI ID:
4302142
Journal Information:
Nuclear Sci. and Eng., Journal Name: Nuclear Sci. and Eng. Vol. Vol: 4
Country of Publication:
Country unknown/Code not available
Language:
English