An improved model for fission product behavior in nuclear fuel under normal and accident conditions
- 1 April 1984
- journal article
- Published by Elsevier in Journal of Nuclear Materials
- Vol. 120 (2-3) , 195-212
- https://doi.org/10.1016/0022-3115(84)90057-6
Abstract
No abstract availableKeywords
This publication has 19 references indexed in Scilit:
- Evaluation of Volatile and Gaseous Fission Product Behavior in Water Reactor Fuel under Normal and Severe Core Accident ConditionsNuclear Technology, 1983
- The Prediction of Transient Fission-Gas Release and Fuel Microcracking Under Severe Core-Accident ConditionsNuclear Technology, 1982
- On the use of grain boundary loss terms in fission gas release and swelling modelsJournal of Nuclear Materials, 1980
- An efficient method for calculating diffusive flow to a spherical boundaryNuclear Engineering and Design, 1980
- The mechanistic prediction of transient fission-gas release from LWR fuelNuclear Engineering and Design, 1980
- Surface, grain boundary and interfacial energies in UO2 and UO2-NiJournal of Nuclear Materials, 1977
- Swelling and gas release in UO2 at low and intermediate temperaturesJournal of Nuclear Materials, 1977
- The release of fission products from nuclear fuel during irradiation by both lattice and grain boundary diffusionJournal of Nuclear Materials, 1975
- Swelling in UO2under conditions of gas releasePhilosophical Magazine, 1974
- The stability of gas bubbles in an irradiation environmentJournal of Nuclear Materials, 1969