Reactor Analysis Support Package (RASP). Volume 5. PWR physics analysis guidelines. Final report
Description
The EPRI Reactor Analysis Support Package (RASP) consists of computer codes and documentation for analyzing reactor physics and thermal-hydraulics problems. The principal application 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 pressurized 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
Availability note (English)
Research Reports Center, Box 50490, Palo Alto, CA 94303.Additional details
Publishing Information
- Imprint Pagination
- 204 p.
- Report number
- EPRI-NP--4498-Vol.5
INIS
- Country of Publication
- United States
- Country of Input or Organization
- United States
- INIS RN
- 18023877
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS; S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Resource subtype / Literary indicator
- Non-conventional Literature
- Descriptors DEI
- BWR TYPE REACTORS; COMPUTERIZED SIMULATION; HEAT TRANSFER; HYDRAULICS; PWR TYPE REACTORS; R CODES; REACTOR LICENSING; REACTOR PHYSICS; REACTOR SAFETY; TRANSIENTS
- Descriptors DEC
- COMPUTER CODES; ENERGY TRANSFER; ENRICHED URANIUM REACTORS; LICENSING; POWER REACTORS; REACTORS; SAFETY; SIMULATION; THERMAL REACTORS; WATER COOLED REACTORS; WATER MODERATED REACTORS