GRABB-a computer code for simulating fission gas disposition in oxide fuel during fast thermal transient
A fission gas code, GRABB, is developed to model intragranular and grain boundary fission gas development and release in a fast thermal transient. Transient direct electrical heating fission gas data, test 33, is simulated with GRABB and GRASS-SST. The computations show that accurate fuel modeling requires consideration of grain edge fission gas and a grain surface bubble interlinkage mechanism. Swelling data are slightly better predicted by GRABB than by GRASS-SST. Both codes underestimate the low temperature gas release data. The GRAS-SSST code underestimates the intermediate temperature gas release while GRABB predictions are within the scatter of the data. The high temperature gas release is overestimated by GRASS-SST while GRABB underestimates it.
- Research Organization:
- University of California, School of Engineering and Applied Science Chemical, Nuclear and Thermal Engineering Department, Los Angeles, California 90024
- OSTI ID:
- 5563380
- Journal Information:
- Nucl. Technol.; (United States), Journal Name: Nucl. Technol.; (United States) Vol. 60:1; ISSN NUTYB
- Country of Publication:
- United States
- Language:
- English
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Related Subjects
220100 -- Nuclear Reactor Technology-- Theory & Calculation
220900* -- Nuclear Reactor Technology-- Reactor Safety
BUBBLES
COMPUTER CODES
COMPUTERIZED SIMULATION
CRYSTAL STRUCTURE
DATA COVARIANCES
ELECTRIC HEATING
FISSION PRODUCT RELEASE
FLUIDS
FUELS
G CODES
GASES
GRAIN BOUNDARIES
HEATING
HIGH TEMPERATURE
LOW TEMPERATURE
MICROSTRUCTURE
MIXED OXIDE FUELS
SIMULATION
SOLID FUELS
SWELLING
TRANSIENTS