Mechanistic prediction of fission-gas behavior during in-cell transient heating tests on LWR fuel using the GRASS-SST and FASTGRASS computer codes
GRASS-SST and FASTGRASS are mechanistic computer codes for predicting fission-gas behavior in UO/sub 2/-base fuels during steady-state and transient conditions. FASTGRASS was developed in order to satisfy the need for a fast-running alternative to GRASS-SST. Althrough based on GRASS-SST, FASTGRASS is approximately an order of magnitude quicker in execution. 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 FASTGRASS calculational procedure is described in this paper, along with models of key physical processes included in both FASTGRASS and GRASS-SST. Predictions of fission-gas release obtained from GRASS-SST and FASTGRASS analyses are compared with experimental observations from a series of DEH tests. The major conclusions is that the computer codes should include an improved model for the evolution of the grain-edge porosity.
- Research Organization:
- Argonne National Lab. (ANL), Argonne, IL (United States)
- Sponsoring Organization:
- USDOE
- DOE Contract Number:
- W-31-109-ENG-38
- OSTI ID:
- 6021758
- Report Number(s):
- CONF-790802-72; TRN: 79-021421
- Resource Relation:
- Conference: International conference on structural mechanics in reactor technology, Berlin, F.R. Germany, 13 Aug 1979
- Country of Publication:
- United States
- Language:
- English
Similar Records
Mechanistic prediction of transient fission-gas release from LWR fuel. [UO/sub 2/]
Steady-state and transient fission gas release and swelling model for LIFE-4. [LMFBR]
Related Subjects
21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
BWR TYPE REACTORS
FUEL ELEMENTS
TRANSIENTS
FISSION PRODUCT RELEASE
PWR TYPE REACTORS
COMPUTER CALCULATIONS
F CODES
FISSION PRODUCTS
G CODES
URANIUM DIOXIDE
ACTINIDE COMPOUNDS
CHALCOGENIDES
COMPUTER CODES
ISOTOPES
OXIDES
OXYGEN COMPOUNDS
RADIOACTIVE MATERIALS
REACTOR COMPONENTS
REACTORS
URANIUM COMPOUNDS
URANIUM OXIDES
WATER COOLED REACTORS
WATER MODERATED REACTORS
220900* - Nuclear Reactor Technology- Reactor Safety
210100 - Power Reactors
Nonbreeding
Light-Water Moderated
Boiling Water Cooled
210200 - Power Reactors
Nonbreeding
Light-Water Moderated
Nonboiling Water Cooled