Quarterly technical progress report on water reactor safety programs sponsored by the Nuclear Regulatory Commission's Division of Reactor Safety Research, October--December 1978
- ed.
Water reactor research performed by EG and G Idaho, Inc., during October--December 1978 is reported. The first small-break experiment was successfully performed in the Semiscale Mod-3 test system, and unusual fluid mass depletion that occurred in the Mod-3 system downcomer during earlier testing was investigated. The LOFT Experimental Program successfully completed the first nuclear loss-of-coolant experiment in the LOFT facility; results show that measured fuel rod cladding temperatures (789 K maximum) were much lower than had been calculated. The Thermal Fuels Behavior Program completed two reactivity initiated accident tests in the Power Burst Facility and preparation for further testing (including a new test series on operational transients). An analysis of two-dimensional temperature distributions in fuel rods was also completed. The Code Development and Analysis Program completed and released the BEACON/MOD2A containment code and the FRAPCON-1 fuel rod steady state analysis code; progress is reported in development of reference code RELAP4 and primary systems code RELAP5. The Code Assessment and Applications Program reports development of the NRC/RSR Data Bank and assessment of the RELAP4/MOD6 and FRAPCON-1 codes. Engineering Support Projects reports completion of an analysis of air--water tests by the 3-D Experiment Project and development of a unique optical probe for viewing multiphase fluid flow phenomena at PWR operating pressure and temperature conditions.
- Research Organization:
- Idaho National Engineering Lab., Idaho Falls (USA)
- DOE Contract Number:
- EY-76-C-07-1570
- OSTI ID:
- 6221960
- Report Number(s):
- NUREG/CR-0512; TREE-1298
- Country of Publication:
- United States
- Language:
- English
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21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
BWR TYPE REACTORS
LOSS OF COOLANT
REACTOR SAFETY
LOFT REACTOR
REACTOR OPERATION
HYDRODYNAMICS
PWR TYPE REACTORS
RESEARCH PROGRAMS
COMPUTER CODES
FLUID FLOW
HEAT TRANSFER
PBF REACTOR
TEMPERATURE DISTRIBUTION
TRANSIENT OVERPOWER ACCIDENTS
ACCIDENTS
ENERGY TRANSFER
FLUID MECHANICS
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OPERATION
PULSED REACTORS
REACTOR ACCIDENTS
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RESEARCH AND TEST REACTORS
SAFETY
TANK TYPE REACTORS
TEST REACTORS
WATER COOLED REACTORS
WATER MODERATED REACTORS
220900* - Nuclear Reactor Technology- Reactor Safety
210100 - Power Reactors
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