Pramana | |
Neutronic simulation of a research reactor core of (232Th, 235U)O2 fuel using MCNPX2.6 code | |
Zohreh Gholamzadeh51  Marzieh Rezazadeh6  Claudio Tenreiro45  Seyed Amir Hossein Feghhi4  Morteza Aref2  Yachine Kadi33  | |
[1] Talca University, St. 720-747, Talca, Chile$$;Faculty of Engineering, Research and Science Branch, Zanjan University, Zanjan, Iran$$;European Organization for Nuclear Research, CERN, 1211 Geneva 23, Switzerland$$;Department of Radiation Application, Shahid Beheshti University, G.C, Tehran, Iran$$;Department of Energy Science, Sungkyunkwan University, 300 Cheoncheon-dong, Suwon, Korea$$;Nuclear Science and Technology Research Institute, Tehran, Iran$$ | |
关键词: Critical; MCNPX2.6; reactor core; thorium oxide.; | |
DOI : | |
学科分类:物理(综合) | |
来源: Indian Academy of Sciences | |
【 摘 要 】
The small reactor design for the remote and less developed areas of the user countries should have simple features in view of the lack of infra-structure and resources. Many researchers consider long core life with no on-site refuelling activity as a primary feature for the small reactor design. Long core life can be achieved by enhancing internal conversion rate of fertile to fissile materials. For that purpose, thorium cycle can be adopted because a high fissile production rate of 233U converted from 232Th can be expected in the thermal energy region. A simple nuclear reactor core arranged 19 assemblies in hexagonal structure, using thorium-based fuel and heavy water as coolant and moderator was simulated using MCNPX2.6 code, aiming an optimized critical assembly. Optimized reflector thickness and gap between assemblies were determined to achieve minimum neutron leakage and void reactivity. The result was a more compact core, where assemblies were designed having 19-fuel pins in 1.25 pitch-to-diameter ratio. Optimum reflector thickness of 15 cm resulted in minimal neutron leakage in view of economic limitations. A 0.5 cm gap between assembles achieved more safety and 2.2% enrichment requirements. The present feasibility study suggests a thermal core of acceptable neutronic parameters to achieve a simple and safe core.
【 授权许可】
Unknown
【 预 览 】
Files | Size | Format | View |
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RO201912040498654ZK.pdf | 978KB | download |