Design basis neutronics calculations for NRU-LOCA experiments
The report describes the neutronics analysis for the LOCA simulation experiments in the NRU reactor. The experimental program will provide greater understanding of nuclear fuel assembly behavior during the heatup, reflood and quench sequence of a hypothetical LOCA. The decay heat and stored heat, which are the energy source in a LOCA will be simulated by fission heat provided by the NRU reactor. The reactor, the test and test operation are described.
- Research Organization:
- Battelle Pacific Northwest Labs., Richland, WA (United States)
- DOE Contract Number:
- EY-76-C-06-1830
- OSTI ID:
- 5765640
- Report Number(s):
- NUREG/CR-1025; PNL-3113; TRN: 79-022223
- Country of Publication:
- United States
- Language:
- English
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21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
LOSS OF COOLANT
PWR TYPE REACTORS
MATHEMATICAL MODELS
NEUTRON FLUX
NRU REACTOR
POWER DENSITY
REACTOR KINETICS
REACTOR SAFETY EXPERIMENTS
SIMULATION
ACCIDENTS
HEAVY WATER COOLED REACTORS
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IRRADIATION REACTORS
ISOTOPE PRODUCTION REACTORS
KINETICS
NATURAL URANIUM REACTORS
RADIATION FLUX
REACTOR ACCIDENTS
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TANK TYPE REACTORS
TEST REACTORS
WATER COOLED REACTORS
WATER MODERATED REACTORS
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210200 - Power Reactors
Nonbreeding
Light-Water Moderated
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