Small break LOCA analysis of the ONRL high flux isotope reactor

Conference · Fri Jan 01 04:00:00 EST 1988

OSTI ID:6980279

Wilson, Jr, T L; Cook, D H; Sozer, A

A digital simulation program, HFIRSYS, was developed using MMS to analyze small break loss of coolant events in the ORNL High Flux Isotope Reactor. The code evaluates the response of the primary reactor system including automatic controls actions resulting from breaks in auxiliary piping connected to the primary. The primary output of the code is the margin to the onset of nucleate boiling expressed as a ratio of heat flux which would cause boiling to the current hot channel heat flux. A description of the model, validation results and a sample transient are presented.

• Research Organization: Oak Ridge National Lab., TN (USA)
• DOE Contract Number: AC05-84OR21400
• OSTI ID: 6980279
• Report Number(s): CONF-8806165-1; ON: DE88012200
• Country of Publication: United States
• Language: English

Related Subjects

21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
220600* -- Nuclear Reactor Technology-- Research
Test & Experimental Reactors
99 GENERAL AND MISCELLANEOUS
990220 -- Computers
Computerized Models
& Computer Programs-- (1987-1989)
ACCIDENTS
BOILING
COMPARATIVE EVALUATIONS
COMPUTER CODES
COMPUTERIZED SIMULATION
DEPRESSURIZATION
ENRICHED URANIUM REACTORS
H CODES
HEAT EXCHANGERS
HEAT FLUX
HFIR REACTOR
HOT CHANNEL
IRRADIATION REACTORS
ISOTOPE PRODUCTION REACTORS
LOSS OF COOLANT
NATIONAL ORGANIZATIONS
NUCLEATE BOILING
ORNL
PHASE TRANSFORMATIONS
REACTOR ACCIDENTS
REACTORS
RESEARCH AND TEST REACTORS
RESEARCH REACTORS
SIMULATION
TANK TYPE REACTORS
TEST REACTORS
TESTING
THERMAL REACTORS
TRANSIENTS
US AEC
US DOE
US ERDA
US ORGANIZATIONS
VALIDATION
WATER COOLED REACTORS
WATER MODERATED REACTORS