Simulation of cold leg manifold break and station blackout sequences in the N Reactor
Technical Report
·
OSTI ID:5319089
This report documents work performed at the Idaho National Engineering Laboratory (INEL) in support of the Westinghouse Hanford Company safety analyses of the N Reactor. This work included: (1) developing a RELAP5/MOD2 N Reactor model from information contained in an existing RETRAN model, (2) modifying the RELAP5/MOD2 computer code for simulation of reflood behavior in horizontal core channels, and (3) performing and analyzing RELAP5/MOD2 transient calculations simulating N Reactor response during two hypothetical accidents. 9 refs., 52 figs., 4 tabs.
- Research Organization:
- EG and G Idaho, Inc., Idaho Falls (USA)
- DOE Contract Number:
- AC07-76ID01570
- OSTI ID:
- 5319089
- Report Number(s):
- EGG-TFM-7891; ON: DE88007741
- Country of Publication:
- United States
- Language:
- English
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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
99 GENERAL AND MISCELLANEOUS
990220 -- Computers
Computerized Models
& Computer Programs-- (1987-1989)
ACCIDENTS
BLACKOUTS
COMPUTER CODES
COMPUTERIZED SIMULATION
COOLING SYSTEMS
DATA
ENERGY LOSSES
ENERGY SYSTEMS
ENERGY TRANSFER
ENRICHED URANIUM REACTORS
FLUID MECHANICS
GRAPHITE MODERATED REACTORS
HEAT TRANSFER
HYDRAULICS
INFORMATION
LEAKS
LOSSES
LWGR TYPE REACTORS
MECHANICS
N-REACTOR
NUMERICAL DATA
PLUTONIUM PRODUCTION REACTORS
POWER LOSSES
POWER REACTORS
PRODUCTION REACTORS
R CODES
REACTOR ACCIDENTS
REACTOR COMPONENTS
REACTOR COOLING SYSTEMS
REACTORS
SIMULATION
THEORETICAL DATA
TRANSIENTS
WATER COOLED REACTORS
22 GENERAL STUDIES OF NUCLEAR REACTORS
220700 -- Nuclear Reactor Technology-- Plutonium & Isotope Production Reactors
220900* -- Nuclear Reactor Technology-- Reactor Safety
99 GENERAL AND MISCELLANEOUS
990220 -- Computers
Computerized Models
& Computer Programs-- (1987-1989)
ACCIDENTS
BLACKOUTS
COMPUTER CODES
COMPUTERIZED SIMULATION
COOLING SYSTEMS
DATA
ENERGY LOSSES
ENERGY SYSTEMS
ENERGY TRANSFER
ENRICHED URANIUM REACTORS
FLUID MECHANICS
GRAPHITE MODERATED REACTORS
HEAT TRANSFER
HYDRAULICS
INFORMATION
LEAKS
LOSSES
LWGR TYPE REACTORS
MECHANICS
N-REACTOR
NUMERICAL DATA
PLUTONIUM PRODUCTION REACTORS
POWER LOSSES
POWER REACTORS
PRODUCTION REACTORS
R CODES
REACTOR ACCIDENTS
REACTOR COMPONENTS
REACTOR COOLING SYSTEMS
REACTORS
SIMULATION
THEORETICAL DATA
TRANSIENTS
WATER COOLED REACTORS