首页> 外文会议>Specialists' Meeting on Reactor Group Constants, Feb 22-23, 2001, Tokai, Japan >Chemical analyses and calculation of isotopic compositions of high-burnup UO_2 fuels and MOX fuels
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Chemical analyses and calculation of isotopic compositions of high-burnup UO_2 fuels and MOX fuels

机译:高燃耗UO_2燃料和MOX燃料的同位素组成的化学分析和计算

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Chemical analysis activities of isotopic compositions of high-burnup UO_2 fuels and MOX fuels in CRIEPI and calculation evaluation are reviewed briefly. C/E values of ORIGEN2, in which original libraries and JENDL-3.2 libraries are used, and other codes with chemical analysis data are reviewed and evaluated. Isotopic compositions of main U and Pu in fuels can be evaluated within 10% relative errors by suitable libraries and codes. Void ratio is effective parameter for C/E values in BWR fuels. JENDL-3.2 library shows remarkable improvement compared with original libraries in isotopic composition evaluations of FP nuclides.
机译:简要回顾了CRIEPI中高燃耗UO_2燃料和MOX燃料的同位素组成的化学分析活性和计算评价。使用原始库和JENDL-3.2库的ORIGEN2的C / E值,并检查和评估带有化学分析数据的其他代码。可以通过合适的库和代码在10%的相对误差范围内评估燃料中主要U和Pu的同位素组成。空隙比是BWR燃料中C / E值的有效参数。与原始库相比,JENDL-3.2库在FP核素的同位素组成评估中显示出显着改进。

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