Extension of the TRANSURANUS plutonium redistribution model for fast reactor performance analysis
| Autor: | Valentino Di Marcello, Jacques van de Laar, Paul Van Uffelen, A. Schubert |
|---|---|
| Rok vydání: | 2012 |
| Předmět: |
Nuclear and High Energy Physics
Engineering Mathematical model business.industry Mechanical Engineering Nuclear engineering chemistry.chemical_element Solid fuel Plutonium Nuclear Energy and Engineering chemistry General Materials Science Post Irradiation Examination Safety Risk Reliability and Quality business Energy source Waste Management and Disposal MOX fuel Simulation Transuranium element Burnup |
| Zdroj: | Nuclear Engineering and Design. 248:149-155 |
| ISSN: | 0029-5493 |
| DOI: | 10.1016/j.nucengdes.2012.03.037 |
| Popis: | The plutonium redistribution model (PUREDI) calculates the steady-state and transient radial plutonium concentration as a function of the radial temperature profile and the time for mixed oxide fuels (MOX). In the context of developing a TRANSURANUS version for Gen-IV fast reactor fuels, PUREDI has been modified and extended to include the effects of the local power density profile and the oxygen-to-metal ratio on plutonium transport. The model has been extensively verified by means of specific numerical tests, and after incorporation in the TRANSURANUS fuel performance code, has been assessed on the basis of post irradiation examinations of the SUPERFACT experiment, showing a good agreement with the experimental data. |
| Databáze: | OpenAIRE |
| Externí odkaz: |
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