Preliminary Core Calculation on Reactivity Compensation for SiC Matrix Fuel Compact HTTR With Erbium Burnable Poison and Plutonium Fissile Material

Y. Nishimura, Mohammad Allaf, Shoichiro Okita, M. Goto, K. Okamoto
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引用次数: 1

Abstract

Proposed higher power density HTGR by removing the graphite sleeve and implementing the SiC matrix fuel compact has neutronics problem on criticality. Present study selected Er burnable poison and Pu fissile material as possible candidate to compensate the reactivity. To ensure core performance of HTTR modeled reactors, the various tests were carried out using Serpent 2 code, and nuclear characteristic data were obtained successfully. The obtained results verified the expected characteristics. It was demonstrated that both Er and Pu solved criticality issue. Furthermore, especially Pu-loaded core showed better burn-up performance compared to current HTGR. One possible option that proposed reactor can also burn Pu safely based on the concept of small-Clean Burn-HTGR was concluded.
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含铒可燃毒物和钚裂变材料的SiC基燃料紧凑型HTTR反应性补偿的初步堆芯计算
提出的去除石墨套筒、采用碳化硅基燃料致密体的高功率密度高温水堆存在中子临界问题。本研究选择了铒可燃毒物和钚可裂变物质作为补偿反应性的可能候选物质。为保证HTTR模型堆的堆芯性能,利用Serpent 2代码进行了各项试验,并成功获得了核特征数据。所得结果验证了预期的特性。结果表明,Er和Pu都解决了临界问题。此外,与现有HTGR相比,加载pu的堆芯表现出更好的燃尽性能。基于小清洁燃烧- htgr的概念,提出了一种可以安全燃烧Pu的可行方案。
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Research on Generalization of Typical Data-Driven Fault Diagnosis Methods for Nuclear Power Plants Heat Transfer Characteristics of Different Horizontal Wires in Pools of Liquid and Supercritical Carbon Dioxide Specifics of Calculating Thermophysical Properties of CO2 and R134a in Critical Point Using NIST REFPROP Radiation Shielding Towards Commonly Available Objects Preliminary Core Calculation on Reactivity Compensation for SiC Matrix Fuel Compact HTTR With Erbium Burnable Poison and Plutonium Fissile Material
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