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| Format: | Artículo científico |
| Sprache: | en |
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Sociedade Brasileira de Proteção Radiológica - SBPR
2021
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| Online-Zugang: | https://www.redalyc.org/articulo.oa?id=722280949008 |
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Inhaltsangabe:
- Thermal hydraulic analysis of a PWR loaded with annular fuel rods W.F Souza M. A. F Veloso A. L Costa C. Pereira Biología STHIRP Annular fuel Thermal model Subchannel code In 2006, the final report of the project named High Performance Fuel Design for Next Generation PWRs was published by the Massachusetts Institute of Technology Center for Advanced Nuclear Energy Systems. This report presented the proposal of the internally and externally cooled annular fuel to allow a substantial increase in power density while maintaining or improving safety margins. The thermal hydraulic conditions were calculated with the aid of the VIPRE (Versatile Internals and Component Program for Reactors) subchannel code, which is a widely used tool in the analysis of nuclear reactor cores. STHIPR-1 (Simulação Termo-Hidráulica de Reatores de Pesquisa) is a subchannel code that has been developed at the Departamento de Engenharia Nuclear /Universidade Federal de Minas Gerais. In order to evaluate the capacity of the STHIRP program, mainly in relation to the thermal model, the new fuel concept was analyzed. The results were compared with those performed with the VIPRE code presented in the reference document. 2021 artículo científico 2319-0612 https://www.redalyc.org/articulo.oa?id=722280949008 en http://www.redalyc.org/revista.oa?id=7222 Brazilian Journal of Radiation Sciences application/pdf Sociedade Brasileira de Proteção Radiológica - SBPR Brazilian Journal of Radiation Sciences (Brasil) Num.2B Vol.9