Steady-state fission gas behavior in uraniumplutoniumzirconium metal fuel elements
| Autor: | A.R. Wazzan, David Okrent, W.G. Steele |
|---|---|
| Rok vydání: | 1989 |
| Předmět: |
Nuclear and High Energy Physics
Zirconium Steady state Materials science Fission Mechanical Engineering chemistry.chemical_element Thermodynamics Metal Nuclear Energy and Engineering chemistry visual_art Thermal visual_art.visual_art_medium medicine Forensic engineering General Materials Science Irradiation Swelling medicine.symptom Safety Risk Reliability and Quality Anisotropy Waste Management and Disposal |
| Zdroj: | Nuclear Engineering and Design. 113:289-295 |
| ISSN: | 0029-5493 |
| DOI: | 10.1016/0029-5493(89)90023-x |
| Popis: | An analysis of fission gas release and induced swelling in steady state irradiated U—Pu—Zr metal fuels is developed and computer coded. The code is used to simulate, with fair success, some gas release and induced swelling data obtained under the IFR program. It is determined that fuel microstructural changes resulting from zirconium migration, anisotropic swelling, and thermal variations are major factors affecting swelling and gas release behavior. |
| Databáze: | OpenAIRE |
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