Accession Number : AD0470470


Title :   NEUTRON FLUX SPECTRA DETERMINATION BY FOIL ACTIVATION. VOLUME II. EXPERIENTAL AND EVALUATED CROSS SECTION LIBRARY OF SELECTED REACTIONS.


Descriptive Note : Technical rept. Mar 64-Jun 65,


Corporate Author : IIT RESEARCH INST CHICAGO ILL


Personal Author(s) : Barrall,R C ; McElroy,W N


Report Date : Aug 1965


Pagination or Media Count : 180


Abstract : A survey was made of nuclear reactions which may be used in measuring neutron flux spectra and fluence. An important application of these data is the determination of neutron flux spectra and fluence for application to radiation effects studies (including dose to tissue). Published microscopic cross section data for 28 reactions have been compiled and are shown graphically. The evaluation of the microscopic data is shown by a line through the data. A tabulation of the evaluated cross section library is provided. Measured values of the resonance integral for selected reactions are reviewed and compared with resonance integrals calculated using the evaluated cross section library. The effects of 0.508, 1.016, and 2.032 mm thick cadmium are discussed. Average cross sections for boron-10 covered foils are calculated. The average cross sections of the 28 reactions in a fission spectrum is calculated. (Author)


Descriptors :   *NEUTRON FLUX , *NUCLEAR CROSS SECTIONS , NEUTRON SPECTRUM , TABLES(DATA) , NEUTRON ACTIVATION , NEUTRON DETECTORS , FOILS(MATERIALS) , MEASUREMENT , CADMIUM , BORON , ATTENUATION , GAMMA NEUTRON REACTIONS


Distribution Statement : APPROVED FOR PUBLIC RELEASE