New cross section processing methodology for HFIR core analysis

Germina Ilas, Jess C. Gehin, R. T. Primm

Research output: Chapter in Book/Report/Conference proceedingConference contributionpeer-review

3 Scopus citations

Abstract

The High-Flux Isotope Reactor is an 85 MW, very high flux reactor operated at the Oak Ridge National Laboratory to support neutron scattering experiments, isotope production, and materials irradiation research. As part of an ongoing engineering design study on the conversion of the reactor from the currently used, highly enriched uranium to a low enriched uranium fuel, work was initiated to develop a new cross section processing methodology. The aim of the study was to ensure an accurate representation of the cross section data for the fuel regions located near the edges of the fuel elements. These regions are characterized by larger in-leakage of thermal neutrons than other parts of the core and neutron flux spectra much different from the average flux in the fuel elements. The new methodology is based on the TRITON/NEWT sequence available in the SCALE code system that allows two-dimensional depletion calculations for arbitrary-mesh geometries. The new cross section processing approach is described and the available results are presented and discussed in this paper.

Original languageEnglish
Title of host publicationInternational Conference on the Physics of Reactors 2008, PHYSOR 08
PublisherPaul Scherrer Institut
Pages2443-2449
Number of pages7
ISBN (Print)9781617821219
StatePublished - 2008
EventInternational Conference on the Physics of Reactors 2008, PHYSOR 08 - Interlaken, Switzerland
Duration: Sep 14 2008Sep 19 2008

Publication series

NameInternational Conference on the Physics of Reactors 2008, PHYSOR 08
Volume3

Conference

ConferenceInternational Conference on the Physics of Reactors 2008, PHYSOR 08
Country/TerritorySwitzerland
CityInterlaken
Period09/14/0809/19/08

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