Published 1988
| Version v1
Report
Restricted
RELAP5: Applications to high fidelity simulation
Description
RELAP5 is a pressurized water reactor system transient simulation code for use in nuclear power plant safety analysis. The latest version, MOD2, may be used to simulate and study a wide variety of abnormal events, including loss-of-coolant accidents, operational transients, and transients in which the entire secondary system must be modeled. In this paper, a basic overview of the code is given, its assessment and application illustrated, and progress toward its use as a high fidelity simulator described. 7 refs., 7 figs
Availability note (English)
MF available from INIS under the Report Number; Available from NTIS, PC A02 - OSTI; 3 as DE89009665.
Files
Additional details
Publishing Information
- Imprint Pagination
- 8 p.
- Report number
- EGG-M--02288
Conference
- Title
- Eastern simulation conference.
- Dates
- 22-24 Apr 1988.
- Place
- Orlando, FL (USA).
INIS
- Country of Publication
- United States
- Country of Input or Organization
- United States
- INIS RN
- 20061097
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS; S99: GENERAL AND MISCELLANEOUS;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- HEAT TRANSFER; HYDRAULICS; LOSS OF COOLANT; MODIFICATIONS; PWR TYPE REACTORS; R CODES; REACTOR SAFETY; TRANSIENTS
- Descriptors DEC
- ACCIDENTS; COMPUTER CODES; ENERGY TRANSFER; ENRICHED URANIUM REACTORS; POWER REACTORS; REACTOR ACCIDENTS; REACTORS; SAFETY; THERMAL REACTORS; WATER COOLED REACTORS; WATER MODERATED REACTORS
Optional Information
- Notes
- Paper copy only, copy does not permit microfiche production.
- Secondary number(s)
- CONF-8804263--1.