COMPUTING ABSOLUTE THERMAL NEUTRON FLUX FROM MEASUREMENTS MADE WITH INDIUM FOILS

Journal Article · Wed Oct 01 04:00:00 EDT 1958 · Nuclear Sci. and Eng.

OSTI ID:4302142

Greenfield, M A; Koontz, R L; Jarrett, A A

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

Related Subjects

ABSORPTION
ACTIVATION
BETA DETECTION
COUNTING RATES
CROSS SECTIONS
EFFICIENCY
ENERGY RANGE
EQUATIONS
ERRORS
FOILS
INDIUM
INDIUM 115
INSTRUMENTS
MEASURED VALUES
NEUTRON FLUX
NUMERICALS
OPERATION
PROPORTIONAL COUNTERS
PULSES
QUANTITATIVE ANALYSIS
RADIATION EFFECTS
THERMAL NEUTRONS
USES
WEIGHT