Published December 1984
| Version v1
Report
RELAP5 thermal-hydraulic analyses of overcooling sequences in a pressurized water reactor
Creators
- 1. Idaho National Engineering Lab., Idaho Falls (USA)
Description
In support of the Pressurized Thermal Shock Integration Study the Idaho National Engineering Laboratory has performed analyses of overcooling transients using the RELAP5/MOD1.6 and MOD2.0 computer codes. These analyses were performed for the H. B. Robinson Unit 2 pressurized water reactor, which is a Westinghouse 3-loop design plant. Results of the RELAP5 computer code as a tool for analyzing integral plant transients requiring a detailed plant model, including complex trip logic and major control systems, are examined. (orig.)
Additional details
Publishing Information
- Imprint Title
- 5th international meeting on thermal nuclear reactor safety. Proceedings. Vol. 1
- Imprint Pagination
- 761 p.
- Journal Page Range
- p. 311-319.
- Report number
- KFK--3880/1
Conference
- Title
- 5. international meeting on thermal nuclear reactor safety.
- Dates
- 9-13 Sep 1984.
- Place
- Karlsruhe (Germany, F.R.).
INIS
- Country of Publication
- Germany
- Country of Input or Organization
- Germany
- INIS RN
- 16068241
- Subject category
- S22: GENERAL STUDIES OF NUCLEAR REACTORS;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- COMPUTER CALCULATIONS; HYDRAULICS; LOSS OF COOLANT; MATHEMATICAL MODELS; PRESSURE RELEASE; PRESSURIZERS; REACTOR SAFETY; ROBINSON-2 REACTOR; STEAM GENERATORS; THERMAL SHOCK; THERMODYNAMICS; TRANSIENTS
- Descriptors DEC
- ACCIDENTS; BOILERS; ENRICHED URANIUM REACTORS; POWER REACTORS; PWR TYPE REACTORS; REACTOR ACCIDENTS; REACTORS; SAFETY; THERMAL REACTORS; VAPOR GENERATORS; WATER COOLED REACTORS; WATER MODERATED REACTORS
Optional Information
- Contract/Grant/Project number
- Contract DE-AC07-76ID01570