STUDIES ON THE LOSS-OF-COOLANT ACCIDENT IN WATER-COOLED NUCLEAR POWER REACTORS. II. (in Japanese)
Journal Article
·
· Denki Shikensho Iho, 32: 975-99(1968).
OSTI ID:4809868
- Research Organization:
- Originating Research Org. not identified
- NSA Number:
- NSA-23-015665
- OSTI ID:
- 4809868
- Journal Information:
- Denki Shikensho Iho, 32: 975-99(1968)., Other Information: Orig. Receipt Date: 31-DEC-69
- Country of Publication:
- Country unknown/Code not available
- Language:
- Japanese
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Related Subjects
N38180* -Power Reactor Development-Safety & Siting
ACCIDENTS
COOLANT LOOPS
FAILURES
FLUID FLOW
PIPES
POWER PLANTS
PRESSURE
PRESSURE VESSELS
REACTOR SAFETY
REACTORS
TRANSIENTS
WATER COOLANT
REACTOR SAFETY/blowdown analysis in pressurized-water power reactors
simulation of double-ended pipe rupture for
(E/T)
REACTORS
PRESSURIZED-WATER/blowdown analysis in power
simulation of double-ended pipe rupture for
(E/T)
REACTORS
POWER/blowdown analysis in pressurized-water
simulation of double-ended pipe rupture for
(E/T)
PIPES/rupture in pressurized- water power reactor cooling system
simulation for blowdown analysis of
(E/T)
ACCIDENTS
COOLANT LOOPS
FAILURES
FLUID FLOW
PIPES
POWER PLANTS
PRESSURE
PRESSURE VESSELS
REACTOR SAFETY
REACTORS
TRANSIENTS
WATER COOLANT
REACTOR SAFETY/blowdown analysis in pressurized-water power reactors
simulation of double-ended pipe rupture for
(E/T)
REACTORS
PRESSURIZED-WATER/blowdown analysis in power
simulation of double-ended pipe rupture for
(E/T)
REACTORS
POWER/blowdown analysis in pressurized-water
simulation of double-ended pipe rupture for
(E/T)
PIPES/rupture in pressurized- water power reactor cooling system
simulation for blowdown analysis of
(E/T)