Calculation of the neutronic behavior of minor actinides burning in a thermal research reactor using the MCNPX 2.6 code
| Autor: | Mahdi Joharifard, Claudio Tenreiro, Zahra Alipoor, Zohreh Gholamzadeh, Seyed Amir Hossein Feghhi |
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| Rok vydání: | 2013 |
| Předmět: |
Nuclear and High Energy Physics
Radiation Nuclear engineering Minor (linear algebra) Monte Carlo method chemistry.chemical_element Minor actinide Actinide Uranium Thorium fuel cycle Nuclear Energy and Engineering chemistry Thermal Environmental science General Materials Science Research reactor Safety Risk Reliability and Quality |
| Zdroj: | Kerntechnik. 78:496-502 |
| ISSN: | 2195-8580 0932-3902 |
| DOI: | 10.3139/124.110366 |
| Popis: | Due to the reduction of accessible uranium resources as well as waste proliferation issues, researchers are looking for more suitable approaches, such as replacement of uranium as breeding fuels. Among the practical fuel matrixes, the thorium fuel matrix is favored for its naturally abundant and minor actinide proliferation resistance. Monte Carlo computational methods are widely used to successfully simulate neutronic behavior of nuclear reactors. Calculation of some neutronic and dynamic parameters of a 37-assembly simulated research reactor consisting of thorium oxide fuel and 1 minor actinide pin have been carried out in the present work using the MCNPX 2.6 code. |
| Databáze: | OpenAIRE |
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