Analysis of the loss of flow in a modular HTR (high temperature reactor) with DSNP (dynamic simulator for nuclear power plants)
Conference
·
· Transactions of the American Nuclear Society; (United States)
OSTI ID:5478411
- Soreq Nuclear Research Centre, Yavne (Israel)
Loss-of-flow (LOF) events in a modular high-temperature gas-cooled reactor designed by Interatom (HTR-module) were simulated and analyzed using the dynamic simulator for nuclear power plants (DSNP) simulation language. The purpose of the study was to investigate the reactor's passive safety features. The modeling methodology used with DSNP is outlined for the components that were included in the simulation. The fully pressurized and depressurized core cases were investigated. Both simulations show that with all decay heat removal systems inoperative, the maximum fuel temperatures do not exceed 1,500{degree}C. Consequently, no significant fission products release is expected even under the most severe accident conditions.
- OSTI ID:
- 5478411
- Report Number(s):
- CONF-891103--
- Conference Information:
- Journal Name: Transactions of the American Nuclear Society; (United States) Journal Volume: 60
- Country of Publication:
- United States
- Language:
- English
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COOLING SYSTEMS
D CODES
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DIFFERENTIAL EQUATIONS
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GAS COOLED REACTORS
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HTGR TYPE REACTORS
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MATHEMATICAL MODELS
ONE-DIMENSIONAL CALCULATIONS
OPERATION
PRESSURIZATION
REACTOR ACCIDENTS
REACTOR COMPONENTS
REACTOR COOLING SYSTEMS
REACTOR CORES
REACTOR OPERATION
REACTOR SAFETY
REACTORS
RHR SYSTEMS
SAFETY
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TWO-DIMENSIONAL CALCULATIONS