COMPUTING ABSOLUTE THERMAL NEUTRON FLUX FROM MEASUREMENTS MADE WITH INDIUM FOILS
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
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