FLASH-3: A FORTRAN IV program for the simulation of reactor plant transients in space and time (LWBR Development Program)
Technical Report
·
OSTI ID:6760956
The FLASH-3 digital computer program, an improved version of FLASH-2, simulates severe transients in pressurized water reactor plants in which the variation of pressure is significant in both space and time. The program is specifically intended to treat the loss-of-coolant accident with emergency core cooling systems, but also can simulate decompression phenomena in pipes, water hammer effects, check valve slam, and general fluid network problems. The program is written in FORTRAN IV for the CDC 6600. (NSA 24: 11218)
- Research Organization:
- Bettis Atomic Power Lab., Pittsburgh, PA (USA)
- DOE Contract Number:
- AT(11-1)-GEN-14
- OSTI ID:
- 6760956
- Report Number(s):
- WAPD-TM-800
- Country of Publication:
- United States
- Language:
- English
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Related Subjects
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Nonbreeding
Light-Water Moderated
Nonboiling Water Cooled
22 GENERAL STUDIES OF NUCLEAR REACTORS
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ACCIDENTS
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CDC COMPUTERS
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COMPUTERS
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F CODES
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MATHEMATICAL MODELS
PRIMARY COOLANT CIRCUITS
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REACTOR ACCIDENTS
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REACTORS
SIMULATION
THERMAL REACTORS
TRANSIENTS
WATER COOLED REACTORS
WATER MODERATED REACTORS
210200 -- Power Reactors
Nonbreeding
Light-Water Moderated
Nonboiling Water Cooled
22 GENERAL STUDIES OF NUCLEAR REACTORS
220900* -- Nuclear Reactor Technology-- Reactor Safety
ACCIDENTS
BREEDER REACTORS
CDC COMPUTERS
COMPUTER CODES
COMPUTERS
COOLING SYSTEMS
F CODES
FORTRAN
LOSS OF COOLANT
LWBR TYPE REACTORS
MATHEMATICAL MODELS
PRIMARY COOLANT CIRCUITS
PROGRAMMING LANGUAGES
PWR TYPE REACTORS
REACTOR ACCIDENTS
REACTOR COMPONENTS
REACTOR COOLING SYSTEMS
REACTORS
SIMULATION
THERMAL REACTORS
TRANSIENTS
WATER COOLED REACTORS
WATER MODERATED REACTORS