Reactor Analysis Support Package (RASP). Volume 4. BWR physics analysis guidelines. Final report
The EPRI Reactor Analysis Support Package (RASP) consists of computer codes and documentation for analyzing reactor physics and thermal-hydraulics problems. The principal applications of these codes involve fuel management, safety analysis for reload submittals and general support for reactor operations. This report explains one aspect of RASP; namely, the reactor physics applications for boiling water reactors. The topics included are the reactor physics models within the RASP codes, the parameters needed for reload safety analysis, the use of reactor physics parameters in each of the transients/accidents that are analyzed for safety analyses and in the interpretation of in-core instrumentation, and the validation of physics models. Although this report refers to the specific codes within RASP, most of the discussion is general enough to be applicable to any calculational methodology.
- Research Organization:
- Diamond (David J.), Port Jefferson, NY (USA)
- OSTI ID:
- 5041956
- Report Number(s):
- EPRI-NP-4498-Vol.4; ON: TI87920087
- Country of Publication:
- United States
- Language:
- English
Similar Records
Reactor Analysis Support Package (RASP). Volume 2. BWR event analysis guidelines. Final report
SIGTRAN: A kinetics linkage code for the Reactor Analysis Support Package (RASP): Final report
Related Subjects
210100 -- Power Reactors
Nonbreeding
Light-Water Moderated
Boiling Water Cooled
210200 -- Power Reactors
Nonbreeding
Light-Water Moderated
Nonboiling Water Cooled
22 GENERAL STUDIES OF NUCLEAR REACTORS
220900* -- Nuclear Reactor Technology-- Reactor Safety
BWR TYPE REACTORS
COMPUTER CODES
ENERGY TRANSFER
FLUID MECHANICS
HEAT TRANSFER
HYDRAULICS
LICENSING
MECHANICS
PHYSICS
PWR TYPE REACTORS
QUALITY ASSURANCE
R CODES
REACTOR LICENSING
REACTOR PHYSICS
REACTOR SAFETY
REACTORS
SAFETY
TRANSIENTS
WATER COOLED REACTORS
WATER MODERATED REACTORS