Masters Theses
Abstract
"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.
Advisor(s)
Edwards, D. R.
Committee Member(s)
Alcorn, Herbert R., 1933-2008
Kim, Hichull
Department(s)
Nuclear Engineering and Radiation Science
Degree Name
M.S. in Nuclear Engineering
Publisher
University of Missouri--Rolla
Publication Date
1968
Pagination
v, 127 pages
Rights
© 1968 Bruce Earl Koopmann, All rights reserved.
Document Type
Thesis - Open Access
File Type
text
Language
English
Subject Headings
Fission products -- Computer programs
Neutron flux -- Measurement
Neutron irradiation -- Measurement
Thesis Number
T 2176
Print OCLC #
6000668
Electronic OCLC #
794078242
Link to Catalog Record
Recommended Citation
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.
https://scholarsmine.mst.edu/masters_theses/5180
