"The development of a computer code was undertaken to calculate the fission product nuclide concentration for spent fuel discharged from a nuclear reactor, as a function of irradiation time, cooling time, neutron flux, and element cross section. The necessary input data was prepared from the basic nuclear data for fission of uranium-235 and plutonium-239. Calculations are also made for total or selective element beta heating and total gamma flux according to user selected input groups. These calculations would be useful in fuel element shielding, cooling, shipping and processing studies"--Abstract, page ii.
Edwards, D. R.
Alcorn, Herbert R., 1933-2008
Nuclear Engineering and Radiation Science
M.S. in Nuclear Engineering
University of Missouri--Rolla
v, 127 pages
© 1968 Bruce Earl Koopmann, All rights reserved.
Thesis - Open Access
Fission products -- Computer programs
Neutron flux -- Measurement
Neutron irradiation -- Measurement
Print OCLC #
Electronic OCLC #
Link to Catalog Record
Koopmann, Bruce Earl, "ZAP - a computer program to predict fission product concentrations as a function of neutron flux, irradiation and cooling times" (1968). Masters Theses. 5180.