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首页> 外文期刊>Transactions of the American nuclear society >A Neutronic Feasibility Study on the Recycling of an Oxide Fuel in a Sodium-Cooled Fast Reactor
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A Neutronic Feasibility Study on the Recycling of an Oxide Fuel in a Sodium-Cooled Fast Reactor

机译:在钠冷快堆中循环使用氧化物燃料的中子学可行性研究

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摘要

The results of the neutronic analysis showed that the recycling of an oxide fuel in an SFR is feasible if the fission products are removed by more than 70% through a dry process as far as the material balance is concerned. However the physics analysis has also shown that some of the physics design parameters are slightly deteriorated. The results of this study indicate that the recycling characteristics of the oxide fuel SFR can be improved if the dry process can remove more fission products from a spent fuel and the reactor configuration is further optimized.
机译:中子学分析的结果表明,就材料平衡而言,如果通过干法将裂变产物去除70%以上,则在SFR中循环使用氧化物燃料是可行的。但是,物理分析还表明,某些物理设计参数略有下降。这项研究的结果表明,如果干法工艺可以从乏燃料中除去更多的裂变产物,并进一步优化反应堆的结构,则可以改善氧化物燃料SFR的循环特性。

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