Published February 1987
| Version v1
Report
RELAP5/MOD2 development
Description
Status of the RELAP5/MOD2 computer code is discussed. While the code is undergoing international assessment, emphasis is on user support and code maintenance with modifications allowed only for error correction and user convenience improvements. User support discussed is the response to user inquiries, maintenance of manuals and the implementation of a PC based newsletter service. The major 1986 user convenience improvement is the self-initialization option. The method is discussed and examples for PWR U tube and once through plants are illustrated. Future plans are also outlined
Additional details
Publishing Information
- Imprint Title
- Proceedings of the US Nuclear Regulatory Commission fourteenth water reactor safety information meeting: Volume 5, Nuclear plant analyzer and code development, International Code Assessment Program, Industry safety research
- Journal Page Range
- p. 15-20.
- Report number
- NUREG/CP--0082-Vol.5
Conference
- Title
- 14. water reactor safety information meeting.
- Dates
- 27-31 Oct 1986.
- Place
- Gaithersburg, MD (USA).
INIS
- Country of Publication
- United States
- Country of Input or Organization
- United States
- INIS RN
- 19002215
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- COMPUTER CODES; COMPUTERIZED SIMULATION; ERRORS; HEAT TRANSFER; HYDRAULICS; LOSS OF COOLANT; PWR TYPE REACTORS; R CODES; REACTOR ACCIDENTS; REACTOR SAFETY; STEAM GENERATORS; TRANSIENTS; US NRC
- Descriptors DEC
- ACCIDENTS; BOILERS; ENERGY TRANSFER; ENRICHED URANIUM REACTORS; NATIONAL ORGANIZATIONS; POWER REACTORS; REACTORS; SAFETY; SIMULATION; THERMAL REACTORS; US ORGANIZATIONS; VAPOR GENERATORS; WATER COOLED REACTORS; WATER MODERATED REACTORS