High Flux Isotope Reactor system RELAP5 input model
A thermal-hydraulic computational model of the High Flux Isotope Reactor (HFIR) has been developed using the RELAP5 program. The purpose of the model is to provide a state-of-the art thermal-hydraulic simulation tool for analyzing selected hypothetical accident scenarios for a revised HFIR Safety Analysis Report (SAR). The model includes (1) a detailed representation of the reactor core and other vessel components, (2) three heat exchanger/pump cells, (3) pressurizing pumps and letdown valves, and (4) secondary coolant system (with less detail than the primary system). Data from HFIR operation, component tests, tests in facility mockups and the HFIR, HFIR specific experiments, and other pertinent experiments performed independent of HFIR were used to construct the model and validate it to the extent permitted by the data. The detailed version of the model has been used to simulate loss-of-coolant accidents (LOCAs), while the abbreviated version has been developed for the operational transients that allow use of a less detailed nodalization. Analysis of station blackout with core long-term decay heat removal via natural convection has been performed using the core and vessel portions of the detailed model.
- Research Organization:
- Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States)
- Sponsoring Organization:
- USDOE; USDOE, Washington, DC (United States)
- DOE Contract Number:
- AC05-84OR21400
- OSTI ID:
- 7042574
- Report Number(s):
- ORNL/TM-11647; ON: DE93007789
- Country of Publication:
- United States
- Language:
- English
Similar Records
Special problems in modeling the high flux isotope reactor with RELAP5
Comparison of Severe Accident Results Among SCDAP/RELAP5, MAAP, and MELCOR Codes
Related Subjects
21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
HFIR REACTOR
REACTOR ACCIDENTS
R CODES
FUEL ELEMENTS
HEAT EXCHANGERS
HEAT TRANSFER
HYDRAULICS
LOSS OF COOLANT
SAFETY ANALYSIS
THERMAL CONDUCTIVITY
ACCIDENTS
COMPUTER CODES
ENERGY TRANSFER
ENRICHED URANIUM REACTORS
FLUID MECHANICS
IRRADIATION REACTORS
ISOTOPE PRODUCTION REACTORS
MECHANICS
PHYSICAL PROPERTIES
REACTOR COMPONENTS
REACTORS
RESEARCH AND TEST REACTORS
RESEARCH REACTORS
TANK TYPE REACTORS
TEST REACTORS
THERMAL REACTORS
THERMODYNAMIC PROPERTIES
WATER COOLED REACTORS
WATER MODERATED REACTORS
220900* - Nuclear Reactor Technology- Reactor Safety
220600 - Nuclear Reactor Technology- Research
Test & Experimental Reactors