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Neutron-Use Optimization with Virtual Experiments to Facilitate Research-Reactor Conversion to Low-Enriched Fuel

机译:通过虚拟实验进行中子使用优化,以促进研究反应器向低浓燃料的转化

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For almost three decades,there have been significant international e?orts to convert research reactors from weapon-usable highly enriched fuel to a fuel based on uranium enriched to less than 20% in the isotope U-235(LEU).The most challenging type of reactors to convert are high-flux research reactors,which,along with some spallation sources,are the most important neutron sources for modern neutron scattering experiments.Advanced Monte-Carlo computer codes are now available that make it possible to track neutrons from the reactor core,through a beam tube,to the instrument and detector.These“virtual experiments”allow optimizing the performance of a research facility as a whole instead of the reactor alone.This may open additional reactors for conversion and could significantly accelerate the“global cleanout”of civilian HEU.This article briefly reviews performance gains obtained for high-flux reactors during previous facility-upgrades.The Monte-Carlo code VITESS is used to compare results for typical neutron scattering experiments using obsolete versus state-of-the-art technologies.The analysis shows that performance gains due to instrument upgrades or neutron guide renewals dwarf potential neutron flux losses due to conversion to low-enriched fuel.
机译:近三十年来,国际上有很多措施将研究反应堆从可用武器的高浓缩燃料转换成同位素U-235(LEU)中铀浓缩至不足20%的燃料。转换的反应堆是高通量研究堆,它与一些散裂源一起,是现代中子散射实验中最重要的中子源。现在可以使用先进的蒙特卡洛计算机代码,使从反应堆中追踪中子成为可能这些“虚拟实验”可以优化研究设施的整体性能,而不是仅仅依靠反应堆。这可以“打开”更多的反应堆进行转化,并可以大大加快“全球清理”的步伐。 ”。本文简要回顾了以前设施升级期间高通量反应堆的性能提升。蒙特卡洛代码VITESS用于比较结果对于使用过时技术与最先进技术进行的典型中子散射实验而言,分析表明,由于仪器升级或中子导管更新而导致的性能提升使转化为低浓燃料的潜在中子通量损失相形见war。

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