Doppler evaluations based on ENDF/B-V (Evaluated Nuclear Data File)
Conference
·
· Transactions of the American Nuclear Society; (United States)
OSTI ID:5491763
- S. Levy, Campbell, CA (USA)
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
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Related Subjects
21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
210100* -- Power Reactors
Nonbreeding
Light-Water Moderated
Boiling Water Cooled
210200 -- Power Reactors
Nonbreeding
Light-Water Moderated
Nonboiling Water Cooled
ACCIDENTS
ACCURACY
BENCHMARKS
BWR TYPE REACTORS
C CODES
COMPUTER CODES
CONTROL ELEMENTS
COOLING SYSTEMS
CROSS SECTIONS
DOPPLER COEFFICIENT
ENERGY SYSTEMS
EPRI
FAILURES
LOSS OF COOLANT
M CODES
MONTE CARLO METHOD
NUCLEAR DATA COLLECTIONS
PHYSICS
PIPES
PRIMARY COOLANT CIRCUITS
PWR TYPE REACTORS
REACTIVITY
REACTIVITY COEFFICIENTS
REACTIVITY INSERTIONS
REACTOR ACCIDENTS
REACTOR COMPONENTS
REACTOR COOLING SYSTEMS
REACTOR PHYSICS
REACTOR SAFETY
REACTORS
RESEARCH PROGRAMS
ROD DROP ACCIDENTS
ROD EJECTION ACCIDENTS
RUPTURES
SAFETY
TRANSIENTS
WATER COOLED REACTORS
WATER MODERATED REACTORS
210100* -- Power Reactors
Nonbreeding
Light-Water Moderated
Boiling Water Cooled
210200 -- Power Reactors
Nonbreeding
Light-Water Moderated
Nonboiling Water Cooled
ACCIDENTS
ACCURACY
BENCHMARKS
BWR TYPE REACTORS
C CODES
COMPUTER CODES
CONTROL ELEMENTS
COOLING SYSTEMS
CROSS SECTIONS
DOPPLER COEFFICIENT
ENERGY SYSTEMS
EPRI
FAILURES
LOSS OF COOLANT
M CODES
MONTE CARLO METHOD
NUCLEAR DATA COLLECTIONS
PHYSICS
PIPES
PRIMARY COOLANT CIRCUITS
PWR TYPE REACTORS
REACTIVITY
REACTIVITY COEFFICIENTS
REACTIVITY INSERTIONS
REACTOR ACCIDENTS
REACTOR COMPONENTS
REACTOR COOLING SYSTEMS
REACTOR PHYSICS
REACTOR SAFETY
REACTORS
RESEARCH PROGRAMS
ROD DROP ACCIDENTS
ROD EJECTION ACCIDENTS
RUPTURES
SAFETY
TRANSIENTS
WATER COOLED REACTORS
WATER MODERATED REACTORS