Comparison of semiscale Mod-1 and LOFT large break loss-of-coolant experiments: a case for nuclear experiments
Conference
·
· Trans. Am. Nucl. Soc.; (United States)
OSTI ID:6946140
None
- Research Organization:
- EGandG Idaho, Idaho Falls, ID 83415
- OSTI ID:
- 6946140
- Report Number(s):
- CONF-811103-
- Conference Information:
- Journal Name: Trans. Am. Nucl. Soc.; (United States) Journal Volume: 39
- Country of Publication:
- United States
- Language:
- English
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Related Subjects
22 GENERAL STUDIES OF NUCLEAR REACTORS
220900* -- Nuclear Reactor Technology-- Reactor Safety
ACCIDENTS
EVALUATION
FUEL-CLADDING INTERACTIONS
LOFT REACTOR
LOSS OF COOLANT
PWR TYPE REACTORS
REACTOR ACCIDENTS
REACTOR SAFETY EXPERIMENTS
REACTORS
RESEARCH AND TEST REACTORS
SAFETY
TANK TYPE REACTORS
TEST REACTORS
THERMAL REACTORS
TRANSIENTS
WATER COOLED REACTORS
WATER MODERATED REACTORS
220900* -- Nuclear Reactor Technology-- Reactor Safety
ACCIDENTS
EVALUATION
FUEL-CLADDING INTERACTIONS
LOFT REACTOR
LOSS OF COOLANT
PWR TYPE REACTORS
REACTOR ACCIDENTS
REACTOR SAFETY EXPERIMENTS
REACTORS
RESEARCH AND TEST REACTORS
SAFETY
TANK TYPE REACTORS
TEST REACTORS
THERMAL REACTORS
TRANSIENTS
WATER COOLED REACTORS
WATER MODERATED REACTORS