MORECA: A computer code for simulating modular high-temperature gas-cooled reactor core heatup accidents
- Oak Ridge National Lab., TN (United States)
The design features of the modular high-temperature gas-cooled reactor (MHTGR) have the potential to make it essentially invulnerable to damage from postulated core heatup accidents. This report describes the ORNL MORECA code, which was developed for analyzing postulated long-term core heatup scenarios for which active cooling systems used to remove afterheat following the accidents can be assumed to the unavailable. Simulations of long-term loss-of-forced-convection accidents, both with and without depressurization of the primary coolant, have shown that maximum core temperatures stay below the point at which any significant fuel failures and fission product releases are expected. Sensitivity studies also have been done to determine the effects of errors in the predictions due both to uncertainties in the modeling and to the assumptions about operational parameters. MORECA models the US Department of Energy reference design of a standard MHTGR.
- Research Organization:
- US Nuclear Regulatory Commission (NRC), Washington, DC (United States). Div. of Regulatory Applications; Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States)
- Sponsoring Organization:
- USNRC; Nuclear Regulatory Commission, Washington, DC (United States)
- DOE Contract Number:
- AC05-84OR21400
- OSTI ID:
- 5955421
- Report Number(s):
- NUREG/CR-5712; ORNL/TM-11823; ON: TI92003495
- Country of Publication:
- United States
- Language:
- English
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Related Subjects
21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
99 GENERAL AND MISCELLANEOUS//MATHEMATICS, COMPUTING, AND INFORMATION SCIENCE
HTGR TYPE REACTORS
REACTOR ACCIDENTS
REACTOR COOLING SYSTEMS
SAFETY ANALYSIS
AFTER-HEAT REMOVAL
DEPRESSURIZATION
HEAT TRANSFER
HYDRAULICS
M CODES
REACTOR SAFETY
SENSITIVITY ANALYSIS
ACCIDENTS
COMPUTER CODES
COOLING SYSTEMS
ENERGY TRANSFER
FLUID MECHANICS
GAS COOLED REACTORS
GRAPHITE MODERATED REACTORS
MECHANICS
REACTOR COMPONENTS
REACTORS
REMOVAL
SAFETY
220900* - Nuclear Reactor Technology- Reactor Safety
210300 - Power Reactors
Nonbreeding
Graphite Moderated
990200 - Mathematics & Computers