Thermal-hydraulic system simulation of the HFIR (high-flux isotope reactor) with RELAP5/MOD2

Conference · Fri Jun 01 00:00:00 EDT 1990 · Transactions of the American Nuclear Society; (USA)

OSTI ID:6371348

Wendel, M W ^[1]; Morris, D G

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1. Oak Ridge Gaseous Diffusion Plant, TN (USA)

A model of the high-flux isotope reactor (HFIR) in Oak Ridge has been developed to simulate loss-of-coolant accidents and operational transients using the RELAP5/MOD2 program. This work constitutes a portion of the analytical studies being performed to update the HFIR thermal-hydraulic safety analysis. RELAP5 permits the determination of the survivability of the core through various transients based on the critical heat flux criteria rather than the more conservative incipient boiling criteria, which have been used previously. Preliminary simulations for small-diameter breaks have been completed, and results are discussed in this paper. These preliminary results indicate that (a) no incipient boiling within the fuel will occur for small-diameter breaks, so (b) the reactor should survive such transients with no fuel damage. Fuel damage is currently assumed to occur in the existing conservative accident analysis for the HFIR. Larger-diameter break simulations are not yet complete, but are currently being performed.

• OSTI ID: 6371348
• Report Number(s): CONF-900608-; CODEN: TANSA; TRN: 91-008365
• Journal Information: Transactions of the American Nuclear Society; (USA), Vol. 61; Conference: American Nuclear Society (ANS) annual meeting, Nashville, TN (USA), 10-14 Jun 1990; ISSN 0003-018X
• Country of Publication: United States
• Language: English

Related Subjects

22 GENERAL STUDIES OF NUCLEAR REACTORS
21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
HFIR REACTOR
REACTOR SAFETY
LOSS OF COOLANT
HEAT TRANSFER
HYDRAULICS
R CODES
BOILING
COMPUTER CODES
COMPUTERIZED SIMULATION
FUEL INTEGRITY
REACTOR ACCIDENTS
REACTOR CORES
ACCIDENTS
ENERGY TRANSFER
ENRICHED URANIUM REACTORS
FLUID MECHANICS
IRRADIATION REACTORS
ISOTOPE PRODUCTION REACTORS
MECHANICS
PHASE TRANSFORMATIONS
REACTOR COMPONENTS
REACTORS
RESEARCH AND TEST REACTORS
RESEARCH REACTORS
SAFETY
SIMULATION
TANK TYPE REACTORS
TEST REACTORS
THERMAL REACTORS
WATER COOLED REACTORS
WATER MODERATED REACTORS
220900* - Nuclear Reactor Technology- Reactor Safety
220700 - Nuclear Reactor Technology- Plutonium & Isotope Production Reactors