Mechanistic prediction of transient fission-gas release from LWR fuel. [UO/sub 2/]
Conference
·
OSTI ID:6865297
The steady-state and transient gas release and swelling subroutine (GRASS-SST) is a mechanistic computer code for the prediction of fission-gas behavior in UO/sub 2/-base fuels. GRASS-SST treats fission-gas release and fuel swelling on an equal basis and simultaneously treats all major mechanisms that influence fission-gas behavior. The GRASS-SST transient analysis has evolved through comparisons of code predictions with the fission-gas release and physical phenomena that occur during reactor operation and transient direct-electrical heating (DEH) testing of irradiated light-water reactor fuel. The GRASS-SST steady-state analysis has undergone verification for end-of-life fission-gas release and intragranular bubble-size distributions. The results of GRASS-SST predictions for transient fission-gas release during DEH tests are in good agreement with experimental data.
- Research Organization:
- Argonne National Lab., Ill. (USA)
- Sponsoring Organization:
- USDOE
- DOE Contract Number:
- W-31109-ENG-38
- OSTI ID:
- 6865297
- Report Number(s):
- CONF-780342--1
- Country of Publication:
- United States
- Language:
- English
Similar Records
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Steady-state and transient fission gas release and swelling model for LIFE-4. [LMFBR]
Technical Report
·
Wed May 31 20:00:00 EDT 1978
·
OSTI ID:6556805
Mechanistic prediction of fission-gas behavior during in-cell transient heating tests on LWR fuel using the GRASS-SST and FASTGRASS computer codes
Conference
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Sun Dec 31 23:00:00 EST 1978
·
OSTI ID:6021758
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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
36 MATERIALS SCIENCE
360206 -- Ceramics
Cermets
& Refractories-- Radiation Effects
ACTINIDE COMPOUNDS
BUBBLE GROWTH
BWR TYPE REACTORS
CHALCOGENIDES
FISSION PRODUCT RELEASE
FUEL ELEMENTS
MATHEMATICAL MODELS
OXIDES
OXYGEN COMPOUNDS
PHYSICAL RADIATION EFFECTS
PWR TYPE REACTORS
RADIATION EFFECTS
REACTOR COMPONENTS
REACTORS
SWELLING
TRANSIENTS
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
36 MATERIALS SCIENCE
360206 -- Ceramics
Cermets
& Refractories-- Radiation Effects
ACTINIDE COMPOUNDS
BUBBLE GROWTH
BWR TYPE REACTORS
CHALCOGENIDES
FISSION PRODUCT RELEASE
FUEL ELEMENTS
MATHEMATICAL MODELS
OXIDES
OXYGEN COMPOUNDS
PHYSICAL RADIATION EFFECTS
PWR TYPE REACTORS
RADIATION EFFECTS
REACTOR COMPONENTS
REACTORS
SWELLING
TRANSIENTS
URANIUM COMPOUNDS
URANIUM DIOXIDE
URANIUM OXIDES
WATER COOLED REACTORS
WATER MODERATED REACTORS