Open AccessDetailed flux calculations for the conceptual design of the Advanced Neutron Source Reactor
Author(s) -
C.A. Wemple
Publication year - 1995
Language(s) - English
Resource type - Reports
DOI - 10.2172/88552
Subject(s) - reflector (photography) , neutron flux , flux (metallurgy) , neutron , neutron source , component (thermodynamics) , nuclear engineering , neutron cross section , spectral line , neutron transport , radiation flux , neutron temperature , physics , nuclear physics , computational physics , materials science , optics , radiation , engineering , light source , thermodynamics , astronomy , metallurgy
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%