Post-test analysis of international standard problem 10 using RELAP4/MOD7. [PWR]
Conference
·
· Trans. Am. Nucl. Soc.; (United States)
OSTI ID:5162495
None
- Research Organization:
- EGandG Idaho, Idaho Falls, ID 83415
- OSTI ID:
- 5162495
- Report Number(s):
- CONF-810606-
- Conference Information:
- Journal Name: Trans. Am. Nucl. Soc.; (United States) Journal Volume: 38
- Country of Publication:
- United States
- Language:
- English
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21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
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210200 -- Power Reactors
Nonbreeding
Light-Water Moderated
Nonboiling Water Cooled
22 GENERAL STUDIES OF NUCLEAR REACTORS
220900* -- Nuclear Reactor Technology-- Reactor Safety
ACCIDENTS
CALCULATION METHODS
CLADDING
COMPUTER CALCULATIONS
DEPOSITION
ENERGY TRANSFER
FLUID MECHANICS
HEAT TRANSFER
HYDRAULICS
LOSS OF COOLANT
MECHANICS
OSCILLATIONS
PHYSICAL PROPERTIES
PWR TYPE REACTORS
QUENCHING
REACTOR ACCIDENTS
REACTOR COMPONENTS
REACTOR CORES
REACTOR SAFETY
REACTORS
SAFETY
STEAM GENERATION
SURFACE COATING
THERMODYNAMIC PROPERTIES
WATER COOLED REACTORS
WATER MODERATED REACTORS