Light-water-reactor safety research program. Quarterly progress report, July-September 1980
Technical Report
·
OSTI ID:5435193
A physically realistic description of fuel swelling and fission-gas release is needed to aid in predicting the behavior of fuel rods and fission gases under certain hypothetical light-water-reactor (LWR) accident conditions. To satisfy this need, a comprehensive computer-base model, the Steady-State and Transient Gas-Release and Swelling Subroutine (GRASS-SST), its faster-running version, FASTGRASS, and correlations based on analyses performed with GRASS-SST, PARAGRASS, are being developed at Argonne National Laboratory (ANL). This model is being incorporated into the Fuel-Rod Analysis Program (FRAP) code being developed by EG and G Idaho, Inc., at the Idaho National Engineering Laboratory (INEL). The analytical effort is supported by a data base and correlations developed from characterization of irradiated LWR fuel and from out-of-reactor transient heating tests of irradiated commercial and experimental LWR fuel under a range of thermal conditions. 7 refs., 2 figs.
- Research Organization:
- Argonne National Lab., IL (USA)
- DOE Contract Number:
- W-31109-ENG-38
- OSTI ID:
- 5435193
- Report Number(s):
- NUREG/CR-1987; ANL-81-15; ON: TI85016017
- Country of Publication:
- United States
- Language:
- English
Similar Records
Mechanistic prediction of fission-gas behavior during in-cell transient heating tests on LWR fuel using the GRASS-SST and FASTGRASS computer codes
Behavior of irradiated LWR fuel pellets during thermal transients
Steady-state and transient fission gas release and swelling model for LIFE-4. [LMFBR]
Conference
·
Sun Dec 31 23:00:00 EST 1978
·
OSTI ID:6021758
Behavior of irradiated LWR fuel pellets during thermal transients
Conference
·
Tue Dec 31 23:00:00 EST 1974
·
OSTI ID:4158087
Steady-state and transient fission gas release and swelling model for LIFE-4. [LMFBR]
Conference
·
Fri Jun 01 00:00:00 EDT 1984
·
OSTI ID:6338991
Related Subjects
21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
210100 -- Power Reactors
Nonbreeding
Light-Water Moderated
Boiling Water Cooled
210200 -- Power Reactors
Nonbreeding
Light-Water Moderated
Nonboiling Water Cooled
22 GENERAL STUDIES OF NUCLEAR REACTORS
220900* -- Nuclear Reactor Technology-- Reactor Safety
36 MATERIALS SCIENCE
360204 -- Ceramics
Cermets
& Refractories-- Physical Properties
ACCIDENTS
ACTINIDE COMPOUNDS
BUBBLE GROWTH
BUBBLES
BWR TYPE REACTORS
CHALCOGENIDES
COMPUTERIZED SIMULATION
CRACK PROPAGATION
CRACKS
CRYSTAL STRUCTURE
FISSION PRODUCT RELEASE
FUEL ELEMENTS
FUEL RODS
GRAIN BOUNDARIES
MICROSTRUCTURE
OXIDES
OXYGEN COMPOUNDS
POROSITY
PWR TYPE REACTORS
REACTOR ACCIDENTS
REACTOR COMPONENTS
REACTOR SAFETY
REACTORS
SAFETY
SIMULATION
STRESSES
SWELLING
THERMAL STRESSES
URANIUM COMPOUNDS
URANIUM DIOXIDE
URANIUM OXIDES
WATER COOLED REACTORS
WATER MODERATED REACTORS
210100 -- Power Reactors
Nonbreeding
Light-Water Moderated
Boiling Water Cooled
210200 -- Power Reactors
Nonbreeding
Light-Water Moderated
Nonboiling Water Cooled
22 GENERAL STUDIES OF NUCLEAR REACTORS
220900* -- Nuclear Reactor Technology-- Reactor Safety
36 MATERIALS SCIENCE
360204 -- Ceramics
Cermets
& Refractories-- Physical Properties
ACCIDENTS
ACTINIDE COMPOUNDS
BUBBLE GROWTH
BUBBLES
BWR TYPE REACTORS
CHALCOGENIDES
COMPUTERIZED SIMULATION
CRACK PROPAGATION
CRACKS
CRYSTAL STRUCTURE
FISSION PRODUCT RELEASE
FUEL ELEMENTS
FUEL RODS
GRAIN BOUNDARIES
MICROSTRUCTURE
OXIDES
OXYGEN COMPOUNDS
POROSITY
PWR TYPE REACTORS
REACTOR ACCIDENTS
REACTOR COMPONENTS
REACTOR SAFETY
REACTORS
SAFETY
SIMULATION
STRESSES
SWELLING
THERMAL STRESSES
URANIUM COMPOUNDS
URANIUM DIOXIDE
URANIUM OXIDES
WATER COOLED REACTORS
WATER MODERATED REACTORS