Analysis of the General Electric Company swell tests with RELAP4/MOD7. [BWR]
Conference
·
· Trans. Am. Nucl. Soc.; (United States)
OSTI ID:5855327
None
- Research Organization:
- EG and G Idaho, Idaho Falls
- OSTI ID:
- 5855327
- Report Number(s):
- CONF-790602-(Summ.)
- Conference Information:
- Journal Name: Trans. Am. Nucl. Soc.; (United States) Journal Volume: 32:489-490
- Country of Publication:
- United States
- Language:
- English
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210100 -- Power Reactors
Nonbreeding
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22 GENERAL STUDIES OF NUCLEAR REACTORS
220900* -- Nuclear Reactor Technology-- Reactor Safety
ACCIDENTS
BWR TYPE REACTORS
COMPUTER CALCULATIONS
ENERGY TRANSFER
FLUID MECHANICS
HEAT TRANSFER
HYDRAULICS
LOSS OF COOLANT
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REACTOR SAFETY
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WATER COOLED REACTORS
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