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首页> 外文期刊>Journal of nuclear engineering and radiation science >Transmutation Study of Minor Actinides in Mixed Oxide Fueled Typical Pressurized Water Reactor Assembly
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Transmutation Study of Minor Actinides in Mixed Oxide Fueled Typical Pressurized Water Reactor Assembly

机译：混合氧化物燃料型典型加压水反应堆组件的次要散浮液的嬗变研究

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摘要

The management of long-lived radionuclides in spent fuel is a key issue to achieve the closed nuclear fuel cycle and the sustainable development of nuclear energy. The partitioning-transmutation method is supposed to efficiently treat the long-lived radionuclides. Accordingly, the transmutation of long-lived minor actinides (MAs) is significant for the postprocessing of spent fuel. In the present work, the transmutations in pressurized water reactor (PWR) mixed oxide (MOX) fuel are investigated through the Monte Carlo neutron transport method. Two types of MAs are homogeneously incorporated into MOX fuel assembly with different mixing ratios. In addition, two types of design of semihomogeneous loading of ~( 237 ) Np in MOX fuels are studied. The results indicate an overall nice efficiency of transmutation in PWR with MOX fuel, especially for ~( 237 ) Np and ~( 241 ) Am, which are primarily generated in the current uranium oxide fuel. In addition, the transmutation efficiency of ~( 237 ) Np is excellent, while its inclusion has no much influence on other MAs. The flattening of power and burnup are achieved by semihomogeneous loading of MAs. The uncertainties of Monte Carlo method are negligible, while those due to nuclear data change little the conclusions of the transmutation of MAs. The transmutation of MAs in MOX fuel is expected to be an efficient method for spent fuel management.
机译：长期放射性核素在花费燃料中的管理是实现核燃料核燃赛和核能可持续发展的关键问题。应有效地治疗长寿放射核素的分区嬗变方法。因此，长寿命的小型散光（MAS）的嬗变对于花费燃料的后处理是显着的。在本作的工作中，通过蒙特卡罗中子传输方法研究加压水反应器（PWR）混合氧化物（MOX）燃料中的差异。用不同的混合比均匀地掺入两种类型的MAS中的MAS燃料组件。此外，研究了MOX燃料中〜（237）NP的两种类型的半均匀负载设计。结果表明PWR与MOX燃料中的嬗变的总体效率，特别是对于〜（237）NP和〜（241）AM，其主要在当前氧化铀燃料中产生。此外，〜（237）NP的嬗变效率优异，而其包含对其他MA没有太大影响。通过半均匀载荷的MAS来实现功率和燃烧的扁平化。 Monte Carlo方法的不确定性可忽略不计，而核数据的核数据变化的结论几乎没有结论。 MAS在MOX燃料中的嬗变预计将是花费燃料管理的有效方法。

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