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Detailed flux calculations for the conceptual design of the Advanced Neutron Source Reactor

By C.A. Wemple

Abstract

A detailed MCNP model of the Advanced Neutron Source Reactor has been developed. All reactor components inside the reflector tank were included, and all components were highly segmented. Neutron and photon multigroup flux spectra have been calculated for each segment in the model, and thermal-to-fast neutron flux ratios were determined for each component segment. Axial profiles of the spectra are provided for all components of the reactor. Individual segment statistical uncertainties were limited wherever possible, and the group fluxes for all important reflector components have a standard deviation below 10%

Topics: Radiation Flux, Gamma Radiation, Neutron Flux, Research Reactors, 22 Nuclear Reactor Technology
Publisher: Oak Ridge National Laboratory
Year: 1995
DOI identifier: 10.2172/88552
OAI identifier:
Provided by: UNT Digital Library
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