N Reactor RELAP5 model benchmark comparisons

Technical Report · Mon Feb 01 04:00:00 EST 1988

DOI:https://doi.org/10.2172/5194568· OSTI ID:5194568

Fletcher, C D; Bolander, M A

This report documents work performed at the Idaho National Engineering Laboratory (INEL) in support of Westinghouse Hanford Company safety analyses for the N Reactor. The portion of the work reported here includes comparisons of RELAP5/MOD2-calculated data with measured plant data for: (1) a plant trip reactor transient from full power operation; and (2) a hot dump test performed prior to plant startup. These qualitative comparisons are valuable because they provide an indication of the capabilities of the RELAP5/MOD2 code to simulate operational and blowdonw transients in the N Reactor. 9 refs., 12 figs., 4 tabs.

• Research Organization: EG and G Idaho, Inc., Idaho Falls (USA)
• DOE Contract Number: AC07-76ID01570
• OSTI ID: 5194568
• Report Number(s): EGG-TFM-7938; ON: DE88007740
• Country of Publication: United States
• Language: English

Related Subjects

21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
22 GENERAL STUDIES OF NUCLEAR REACTORS
220700 -- Nuclear Reactor Technology-- Plutonium & Isotope Production Reactors
220900* -- Nuclear Reactor Technology-- Reactor Safety
ACCIDENTS
COMPUTER CODES
DATA
ENERGY TRANSFER
ENRICHED URANIUM REACTORS
FLUID MECHANICS
GRAPHITE MODERATED REACTORS
HEAT TRANSFER
HYDRAULICS
INFORMATION
LWGR TYPE REACTORS
MECHANICS
N-REACTOR
NUMERICAL DATA
PLUTONIUM PRODUCTION REACTORS
POWER REACTORS
PRODUCTION REACTORS
R CODES
REACTOR ACCIDENTS
REACTOR SAFETY
REACTOR SHUTDOWN
REACTORS
SAFETY
SHUTDOWNS
THEORETICAL DATA
TRANSIENTS
WATER COOLED REACTORS