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Doppler evaluations based on ENDF/B-V (Evaluated Nuclear Data File)

Conference · · Transactions of the American Nuclear Society; (United States)
OSTI ID:5491763
The Doppler coefficient of reactivity is a crucial parameter in the evaluation of several potential transients in light water reactors (LWRs), including the pressurized water reactor (PWR) control rod ejection accident, the PWR steam-line break accident, and the boiling water reactor (BWR) control rod drop accident. At the same time, it is relatively small in magnitude and cannot be measured directly in an operating reactor. Instead, it must be inferred from a variety of other measured parameters. A recent study has raised questions about the consistency and adequacy of the Doppler coefficient of reactivity computed by a variety of LWR spectrum codes. This paper addresses that concern by constructing a set of numerical benchmarks for the Doppler coefficient using the most accurate means available: a continuous-energy Monte Carlo calculation with ENDF/B-V cross section data.
OSTI ID:
5491763
Report Number(s):
CONF-891103--
Conference Information:
Journal Name: Transactions of the American Nuclear Society; (United States) Journal Volume: 60
Country of Publication:
United States
Language:
English