FRAP-GCFR: a code for the transient analysis of gas-cooled fast reactors
Conference
·
OSTI ID:6016329
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:
- Not Available; USDOE
- DOE Contract Number:
- EY-76-C-07-1570
- OSTI ID:
- 6016329
- Report Number(s):
- CONF-790816-3
- Country of Publication:
- United States
- Language:
- English
Similar Records
FRAP-T5: a computer code for the transient analysis of oxide fuel rods
FRAP-S2: a computer code for the steady state analysis of oxide fuel rods
Review of FRAP-T4 performance based on fuel behavior tests conducted in the PBF. [PWR; BWR]
Technical Report
·
Fri Jun 01 00:00:00 EDT 1979
·
OSTI ID:6042488
FRAP-S2: a computer code for the steady state analysis of oxide fuel rods
Technical Report
·
Fri Jul 01 00:00:00 EDT 1977
·
OSTI ID:7322372
Review of FRAP-T4 performance based on fuel behavior tests conducted in the PBF. [PWR; BWR]
Technical Report
·
Sat Sep 01 00:00:00 EDT 1979
·
OSTI ID:5810916
Related Subjects
21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
210500 -- Power Reactors
Breeding
22 GENERAL STUDIES OF NUCLEAR REACTORS
220900* -- Nuclear Reactor Technology-- Reactor Safety
ACCIDENTS
BREEDER REACTORS
COMPUTER CODES
ENERGY TRANSFER
EPITHERMAL REACTORS
F CODES
FAST REACTORS
FBR TYPE REACTORS
FLOW BLOCKAGE
FUEL ELEMENT FAILURE
GAS COOLED REACTORS
GCFR REACTOR
GCFR TYPE REACTORS
HEAT TRANSFER
HELIUM COOLED REACTORS
MATHEMATICAL MODELS
REACTOR ACCIDENTS
REACTORS
TRANSIENTS
210500 -- Power Reactors
Breeding
22 GENERAL STUDIES OF NUCLEAR REACTORS
220900* -- Nuclear Reactor Technology-- Reactor Safety
ACCIDENTS
BREEDER REACTORS
COMPUTER CODES
ENERGY TRANSFER
EPITHERMAL REACTORS
F CODES
FAST REACTORS
FBR TYPE REACTORS
FLOW BLOCKAGE
FUEL ELEMENT FAILURE
GAS COOLED REACTORS
GCFR REACTOR
GCFR TYPE REACTORS
HEAT TRANSFER
HELIUM COOLED REACTORS
MATHEMATICAL MODELS
REACTOR ACCIDENTS
REACTORS
TRANSIENTS