Special problems in modeling the high flux isotope reactor with RELAP5

Conference · Mon Jan 01 00:00:00 EST 1990

OSTI ID:6851331

Wendel, M W ^[1]; Morris, D G ^[2]

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

A RELAP5 thermal-hydraulic model of the High Flux Isotope Reactor (HFIR) has been developed to perform calculations for the HFIR Final Safety Analysis Report (FSAR). Modeling problems specific to the HFIR exist because it is a liquid-solid system and experiences low (often subatmospheric) pressures during a loss-of-coolant accident (LOCA). The problem discussed include (1)adequately modeling depressurization of the system, (2) predicting the occurrence of internal choking of the primary coolant flow, and (3) modeling the effects of pump cavitation, which occurs for some LOCAs. An accurate model of the system stiffness has been developed and tested using the RELAP5 control systems capability and seems to be adequate for predicting the behavior of the primary coolant system during a LOCA. The problems with internal choking and pump cavitation have been addressed, but are not yet resolved. 11 refs., 7 figs.

• Research Organization: Oak Ridge Gaseous Diffusion Plant, TN (USA)
• Sponsoring Organization: DOE/NE
• DOE Contract Number: AC05-84OT21400
• OSTI ID: 6851331
• Report Number(s): K/CSD/INF-90/28; CONF-9009219-1; ON: DE90014316; TRN: 90-025051
• Resource Relation: Conference: 1990 joint RELAP5 and TRAC-BWR international user seminar, Chicago, IL (USA), 17-21 Sep 1990
• Country of Publication: United States
• Language: English

Related Subjects

22 GENERAL STUDIES OF NUCLEAR REACTORS
21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
99 GENERAL AND MISCELLANEOUS//MATHEMATICS, COMPUTING, AND INFORMATION SCIENCE
HFIR REACTOR
LOSS OF COOLANT
R CODES
CAVITATION
DEPRESSURIZATION
EVALUATION
HEAT TRANSFER
HYDRAULICS
O CODES
PRIMARY COOLANT CIRCUITS
PUMPS
REACTOR SAFETY
ACCIDENTS
COMPUTER CODES
COOLING SYSTEMS
ENERGY SYSTEMS
ENERGY TRANSFER
ENRICHED URANIUM REACTORS
FLUID MECHANICS
IRRADIATION REACTORS
ISOTOPE PRODUCTION REACTORS
MECHANICS
REACTOR ACCIDENTS
REACTOR COMPONENTS
REACTOR COOLING SYSTEMS
REACTORS
RESEARCH AND TEST REACTORS
RESEARCH REACTORS
SAFETY
TANK TYPE REACTORS
TEST REACTORS
THERMAL REACTORS
WATER COOLED REACTORS
WATER MODERATED REACTORS
220900* - Nuclear Reactor Technology- Reactor Safety
220600 - Nuclear Reactor Technology- Research
Test & Experimental Reactors
990200 - Mathematics & Computers