"Neutron flux in the side regions of the High Temperature Gas Cooled Reactor's (HTGR) Prestressed Concrete Reactor Vessel (PCRV) was determined using the Monte Carlo method. One quarter of the PCRV was modeled, with all major structures inside it, e.g. steam generator, auxiliary cooling loop, etc. imaged at their exact position and size. Initial neutron energies range from .001 eV to 3 MeV. Three neutron interactions were considered: absorbtion, elastic scattering, and inelastic scattering.
The flux was calculated for two different PCRV temperatures, 155° F and 647° F. The thermal flux showed a minor increase at the higher temperature. In general, the results agree with previous calculations which were made using the transport method"--Abstract, page ii.
Edwards, D. R.
Malisch, Ward R.
Nuclear Engineering and Radiation Science
M.S. in Nuclear Engineering
University of Missouri--Rolla
ix, 75 pages
© 1974 Richard Robert Kent, Jr., All rights reserved.
Thesis - Open Access
Neutron flux -- Measurement
Nuclear reactors -- Shielding (Radiation) -- Testing
Gas cooled reactors
Print OCLC #
Electronic OCLC #
Link to Catalog Record
Kent, Richard Robert Jr., "Calculation of the neutron flux in the side regions of the prestressed concrete reactor vessel of a high temperature gas cooled reactor" (1974). Masters Theses. 3455.