GRABB—A Computer Code for Simulating Fission Gas Dispostion in Oxide Fuel During Fast Thermal Transient
- 1 January 1983
- journal article
- research article
- Published by Taylor & Francis in Nuclear Technology
- Vol. 60 (1) , 69-83
- https://doi.org/10.13182/nt83-a33103
Abstract
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 GRASS-SST 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.Keywords
This publication has 18 references indexed in Scilit:
- Yielding of steel sheets containing slitsPublished by Elsevier ,2002
- A simple operational gas release and swelling model: II. Grain boundary gasJournal of Nuclear Materials, 1980
- Gas release mechanisms in UO2—a critical reviewRadiation Effects, 1980
- Swelling and gas release in UO2 at low and intermediate temperaturesJournal of Nuclear Materials, 1977
- Swelling in UO2under conditions of gas releasePhilosophical Magazine, 1974
- The distribution of intragranular fission gas bubbles in UO2 during irradiationJournal of Nuclear Materials, 1971
- The stability of gas bubbles in an irradiation environmentJournal of Nuclear Materials, 1969
- The yield and flow of single crystals of uranium dioxideJournal of Nuclear Materials, 1968
- Local yielding and extension of a crack under plane stressActa Metallurgica, 1965
- The influence of grain boundaries on the nucleation of secondary phasesActa Metallurgica, 1955