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Analytical Study of Criticality Experiments of Organic and Light-Water-Moderated Mixed-Oxide Fuel Pin Arrays

Conference · · Transactions of the American Nuclear Society
OSTI ID:5579046
As part of a joint criticality data development program between the Power Reactor and Nuclear Fuel Development Corp. of Japan and the US Dept. of Energy, critical experiments have been conducted with organically moderated fast test reactor (FTR) mixed-oxide fuel pin arrays. The neutronic characteristics of an organic moderator can be examined by comparing the results of these experiments with the results of the same type of experiments performed with light-water-moderated systems. In recent experiments performed at the Battelle Pacific Northwest Laboratory's Critical Mass Laboratory, five distances of the lattice pitches were utilized that span from soft to hard neutron energy spectra. These lattice pitches range from a volume ratio of 1.62 to 18.13. The organic solution consisted of approx. 32 vol % tributyl phosphate (TBP) and 68 vol % normal paraffin hydrocarbon (NPH). Results obtained by benchmark analyses of these experiments are discussed in this paper.
Research Organization:
PNC, Oarai (Japan)
Sponsoring Organization:
USDOE National Nuclear Security Administration (NNSA), Nuclear Criticality Safety Program (NCSP)
OSTI ID:
5579046
Report Number(s):
CONF-870601-
Conference Information:
Journal Name: Transactions of the American Nuclear Society Journal Volume: 54
Country of Publication:
United States
Language:
English