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核技术  2015 

热堆中钍铀转化规律

DOI: 10.11889/j.0253-3219.2015.hjs.38.050601, PP. 50601-50601

Keywords: 中子注量率,中子能谱,钍铀转化率

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Abstract:

钍铀燃料循环以其优异的物理和化学特性,受到核能界的广泛关注。本文利用单群的点燃耗计算程序ORIGEN,分别研究了钍燃料在沸水堆(BoilingWaterReactor,BWR)、压水堆(PressurizedWaterReactor,PWR)和加拿大重水铀反应堆(CanadaDeuteriumOxideUranium,CANDU,又称坎杜堆)能谱中辐照时,232Th、233Th、233Pa、233U等核素生成量随中子注量率和中子能谱的变化规律,并探索了多次“辐照-冷却”循环对钍铀转化率的影响。计算结果表明,能谱相同时,233Th和233Pa存量的最大值与注量率有关;233U存量的最大值与注量率无关,大概在注量(注量率×时间)为4×1016n?cm?2左右;注量率相同时,能谱越硬,233U存量的最大值越大。采取循环“辐照-冷却”可以提高233Th-233U的转化率,对于相同的总辐照时间,每次循环周期内的辐照时间越短,相对于总辐照时间相同的单次辐照,转化率增量提高越明显;当总辐照时间超过两个月时,循环辐照对转化率增量的作用较小,与单次辐照不冷却相比,转化率相对增量不超过1倍。

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