FRAP-GCFR: a code for the transient analysis of gas-cooled fast reactors
The fuel rod analysis computer program (FRAP-T) has been modified to analyze transient fuel rod behavior in the gas cooled fast reactor (GCFR). Major features modeled include the effects of helium coolant, ribbed cladding, pressure equalization system, and 316 stainless-steel material properties. The code capabilities include models of elastic-plastic-creep deformation behavior, two-dimensional heat conduction, rod ballooning, and transient axial gas flow. The models are particularly relevant to GCFR transient analysis in that partial or full blockage of the pressure equalization system could cause a significant pressure differential to exist during a helium depressurization, the GCFR design basis accident. An analysis of the design basis accident illustrating the predictive capabilities of the code is presented.
- Research Organization:
- Idaho National Engineering Lab., Idaho Falls (USA)
- Sponsoring Organization:
- USDOE
- DOE Contract Number:
- EY-76-C-07-1570
- OSTI ID:
- 6016329
- Report Number(s):
- CONF-790816-3; TRN: 79-015723
- Resource Relation:
- Conference: International meeting on fast reactor safety technology, Seattle, WA, USA, 19 Aug 1979
- Country of Publication:
- United States
- Language:
- English
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Related Subjects
21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
GCFR REACTOR
REACTOR ACCIDENTS
GCFR TYPE REACTORS
MATHEMATICAL MODELS
COMPUTER CODES
F CODES
FLOW BLOCKAGE
FUEL ELEMENT FAILURE
HEAT TRANSFER
TRANSIENTS
ACCIDENTS
BREEDER REACTORS
ENERGY TRANSFER
EPITHERMAL REACTORS
FAST REACTORS
FBR TYPE REACTORS
GAS COOLED REACTORS
HELIUM COOLED REACTORS
REACTORS
220900* - Nuclear Reactor Technology- Reactor Safety
210500 - Power Reactors
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