Reactor safety research programs. Quarterly report, April 1--June 30, 1978
Technical Report
·
OSTI ID:6385913
- ed.
Progress is summarized in the following LWR safety-related studies: ultimate heat sink performance measurements; steam generator tube integrity; acoustic emission; irradiation results of experimental verification of steady state codes; ex-reactor verification of steady state codes; determination of thermal gap and contact conductance; code development; fuel subassembly procurement and irradiation test program; LOCA simulation in NRU; and core thermal model development; non-destructive testing for oxidation of graphite samples is described.
- Research Organization:
- Battelle Pacific Northwest Labs., Richland, WA (USA)
- DOE Contract Number:
- EY-76-C-06-1830
- OSTI ID:
- 6385913
- Report Number(s):
- NUREG/CR-0341; PNL-2653-2
- Country of Publication:
- United States
- Language:
- English
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22 GENERAL STUDIES OF NUCLEAR REACTORS
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BWR TYPE REACTORS
REACTOR SAFETY
PWR TYPE REACTORS
RESEARCH PROGRAMS
HTGR TYPE REACTORS
ACOUSTIC EMISSION TESTING
COMPUTER CODES
COOLING PONDS
FAILURES
FUEL PELLETS
FUEL RODS
HEAT TRANSFER
HYDRAULICS
LOSS OF COOLANT
MATHEMATICAL MODELS
PERFORMANCE TESTING
PRESSURE VESSELS
STEAM GENERATORS
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TUBES
GRAPHITE
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OXIDATION
REACTOR MATERIALS
ACCIDENTS
ACOUSTIC TESTING
BOILERS
CARBON
CHEMICAL REACTIONS
CONTAINERS
ELEMENTS
ENERGY TRANSFER
FLUID MECHANICS
FUEL ELEMENTS
GAS COOLED REACTORS
GRAPHITE MODERATED REACTORS
MATERIALS TESTING
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PHYSICAL PROPERTIES
PONDS
REACTOR ACCIDENTS
REACTOR COMPONENTS
REACTORS
SAFETY
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TESTING
THERMODYNAMIC PROPERTIES
VAPOR GENERATORS
WATER COOLED REACTORS
WATER MODERATED REACTORS
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21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
BWR TYPE REACTORS
REACTOR SAFETY
PWR TYPE REACTORS
RESEARCH PROGRAMS
HTGR TYPE REACTORS
ACOUSTIC EMISSION TESTING
COMPUTER CODES
COOLING PONDS
FAILURES
FUEL PELLETS
FUEL RODS
HEAT TRANSFER
HYDRAULICS
LOSS OF COOLANT
MATHEMATICAL MODELS
PERFORMANCE TESTING
PRESSURE VESSELS
STEAM GENERATORS
THERMAL CONDUCTIVITY
TUBES
GRAPHITE
NONDESTRUCTIVE TESTING
OXIDATION
REACTOR MATERIALS
ACCIDENTS
ACOUSTIC TESTING
BOILERS
CARBON
CHEMICAL REACTIONS
CONTAINERS
ELEMENTS
ENERGY TRANSFER
FLUID MECHANICS
FUEL ELEMENTS
GAS COOLED REACTORS
GRAPHITE MODERATED REACTORS
MATERIALS TESTING
MECHANICS
NONMETALS
PELLETS
PHYSICAL PROPERTIES
PONDS
REACTOR ACCIDENTS
REACTOR COMPONENTS
REACTORS
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SURFACE WATERS
TESTING
THERMODYNAMIC PROPERTIES
VAPOR GENERATORS
WATER COOLED REACTORS
WATER MODERATED REACTORS
WATER RESERVOIRS
220900* - Nuclear Reactor Technology- Reactor Safety
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210200 - Power Reactors
Nonbreeding
Light-Water Moderated
Nonboiling Water Cooled
210300 - Power Reactors
Nonbreeding
Graphite Moderated