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Evaluation of the uncertainties in the source distribution for pressure vessel neutron fluence calculations

Journal Article · · Nuclear Technology
OSTI ID:31982
; ;  [1]
  1. Pennsylvania State Univ., University Park, PA (United States). Nuclear Engineering Dept.

The methodology used to prepare the source for neutron fluence calculation at the reactor pressure vessel is examined, and its effect on the calculated cavity dosimeter reaction rate is evaluated. Different source distributions for the Three Mile Island Unit 1 and Davis-Besse reactors and a simulated low low-leakage loading pattern are analyzed based on different levels of homogenization, different isotopic averaging approaches, contribution of {sup 238}U, use of the LEPRICON C factor formulation, and the SAILOR spectrum. Fuel isotopics can significantly affect the source distributions (through the fission spectrum), thereby leading to uncertainties of {approximately}7% in the calculated cavity dosimetry reaction rates. Higher uncertainties (>10%) are expected due to both the C factor and fission spectrum when the low low-leakage fuel designs are utilized.

OSTI ID:
31982
Journal Information:
Nuclear Technology, Journal Name: Nuclear Technology Journal Issue: 1 Vol. 109; ISSN 0029-5450; ISSN NUTYBB
Country of Publication:
United States
Language:
English