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Three-Dimensional Discrete Ordinates Radiation Transport Calculations of Neutron Fluxes for Beginnig-of-Cycle at Several Pressure Vessel Surveillance Positions in the High Flux Isotope Reactor Pages: 7 Published: Jan 1994
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View License Agreement Source: STP1228-EB Abstract The objective of this research was to determine improved thermal, epithermal, and fast fluxes and several responses at mechanical test surveillance location keys 2, 4, 5, and 7 of the pressure vessel of the Oak Ridge National Laboratory High Flux Isotope Reactor (HFIR) for the beginning of the fuel cycle. The purpose of the research was to provide essential flux data in support of radiation embrittlenient studies of the pressure vessel shell and beam tubes at some of the important locations. Keywords: radiation damage, radiation transport, reactor pressure vessel, neutron fluxes, damage surveillance, dosimetry Paper ID: STP15106S Committee/Subcommittee: E10.08 DOI: 10.1520/STP15106S  ASTM International is a member of CrossRef. | ||