Characterization of end-of-life rod internal pressure in PWR fuel
| Autor: | Joseph Y. R. Rashid, Albert J. Machiels, William F. Lyon, Dion Sunderland |
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| Rok vydání: | 2017 |
| Předmět: |
Nuclear and High Energy Physics
Materials science Ideal gas law 020209 energy Mechanical Engineering Nuclear engineering Pressurized water reactor Internal pressure Radioactive waste 02 engineering and technology Cladding (fiber optics) 01 natural sciences Spent nuclear fuel 010305 fluids & plasmas law.invention Surface coating Nuclear Energy and Engineering law 0103 physical sciences 0202 electrical engineering electronic engineering information engineering General Materials Science sense organs Safety Risk Reliability and Quality Waste Management and Disposal Burnup |
| Zdroj: | Nuclear Engineering and Design. 324:250-259 |
| ISSN: | 0029-5493 |
| Popis: | The end-of-life (EOL) fuel rod internal pressure (RIP) is a critical parameter for assessing the performance of spent fuel during dry storage and transportation. At issue are several potential degradation mechanisms that are strongly dependent on rod internal pressure. Experimental EOL RIP data of pressurized water reactor (PWR) spent fuel rods were compiled from available non-proprietary sources and used to develop a model that quantifies the fuel rod’s gas content in terms of its molar mass, from which the rod internal pressure can be derived using the ideal gas law. Application of the model is illustrated using temperature profiles measured in a spent fuel storage system. The results show that for rod-average burnup of ∼60 GWd/MTU and peak cladding temperature as high as 400 °C, cladding stresses are less than 100 MPa for the clear majority of spent PWR fuel. |
| Databáze: | OpenAIRE |
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