Analysis of intergranular fission-gas bubble-size distributions in irradiated uranium–molybdenum alloy fuel
- 15 April 2009
- journal article
- Published by Elsevier in Journal of Nuclear Materials
- Vol. 385 (3) , 563-571
- https://doi.org/10.1016/j.jnucmat.2009.01.001
Abstract
No abstract availableKeywords
This publication has 13 references indexed in Scilit:
- Characterization of intergranular fission gas bubbles in U-Mo fuel.Published by Office of Scientific and Technical Information (OSTI) ,2008
- Transmission electron microscopy investigation of irradiated U–7wt%Mo dispersion fuelJournal of Nuclear Materials, 2008
- Matrix swelling rate and cavity volume balance of UO2 fuels at high burn-upJournal of Nuclear Materials, 2005
- The effect of irradiation-induced gas-atom re-solution on grain-boundary bubble growthJournal of Nuclear Materials, 2003
- Evolution of helium bubbles in aluminum during heavy-ion irradiationPhysical Review B, 1994
- On the in-pile nucleation and growth of grain-boundary bubblesJournal of Nuclear Materials, 1983
- Fundamental aspects of nuclear reactor fuel elementsPublished by Office of Scientific and Technical Information (OSTI) ,1976
- A calculation on the size distribution of intragranular bubbles in irradiated UO2Journal of Nuclear Materials, 1971
- A Calculation on the Migration of Fission Gas in Material Exhibiting Precipitation and Re-solution of Gas Atoms Under IrradiationNuclear Science and Engineering, 1969
- The growth of fission gas bubbles in irradiated uranium dioxidePhilosophical Magazine, 1969