TY - GEN
T1 - New cross section processing methodology for HFIR core analysis
AU - Ilas, Germina
AU - Gehin, Jess C.
AU - Primm, R. T.
PY - 2008
Y1 - 2008
N2 - 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.
AB - 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.
UR - http://www.scopus.com/inward/record.url?scp=79953862366&partnerID=8YFLogxK
M3 - Conference contribution
AN - SCOPUS:79953862366
SN - 9781617821219
T3 - International Conference on the Physics of Reactors 2008, PHYSOR 08
SP - 2443
EP - 2449
BT - International Conference on the Physics of Reactors 2008, PHYSOR 08
PB - Paul Scherrer Institut
T2 - International Conference on the Physics of Reactors 2008, PHYSOR 08
Y2 - 14 September 2008 through 19 September 2008
ER -