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Assessment of criticality and burn up behavior of candu reactors with nuclear waste trans uranium fuel

机译:评估含核废铀燃料的坎杜反应堆的临界度和燃尽行为

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摘要

Large quantities of nuclear waste plutonium and minor actinides (MAs) have been accumulated in the civilian light water reactors (LWRs) and CANDU reactors. These trans uranium (TRU) elements are all fissionable, and thus can be considered as fissile fuel materials in form of mixed fuel with thorium or nat-uranium in the latter. CANDU fuel compacts made of tristructural-isotropic (TRISO) type pellets would withstand very high burn ups without fuel change. As carbide fuels allow higher fissile material density than oxide fuels, following fuel compositions have been selected for investigations: ① 90% nat-UC + 10% TRUC, ② 70% nat-UC + 30% TRUC and ③ 50% nat-UC + 50% TRUC. Higher TRUC charge leads to longer power plant operation periods without fuel change. The behavior of the criticality k_∞and the burn up values of the reactor have been pursued by full power operation for > ~12 years. For these selected fuel compositions, the reactor criticality starts by k_∞ = 1.4443,1.4872 and 1.5238, where corresponding reactor operation times and burn up values have been calculated as 2.8 years, 8 years and 12.5 years, and 62,430 MW.D/MT, 176,000 and 280,000 MW.D/ MT, with fuel consumption rates of ~ 16, 5.68 and 3.57 g/MW.D respectively. These high burn ups would reduce the nuclear waste mass per unit energy output drastically. The study has show clearly that TRU in form of TRISO fuel pellets will provide sufficient criticality as well as reasonable burn up for CANDU reactors in order to justify their consideration as alternative fuel.
机译:在民用轻水反应堆(LWR)和CANDU反应堆中已积累了大量核废waste和次act系元素(MA)。这些铀(TRU)元素都是可裂变的,因此可以认为是与fuel或na铀混合的燃料形式的易裂变燃料材料。由三向同性(TRISO)型颗粒制成的CANDU燃料压块将承受非常高的燃尽,而无需更换燃料。由于碳化物燃料比氧化物燃料具有更高的易裂变材料密度,因此选择了以下燃料成分进行研究:①90%nat-UC + 10%TRUC,②70%nat-UC + 30%TRUC和③50%nat-UC + 50%TRUC。较高的TRUC收费会导致电厂运行时间更长,而无需更换燃料。临界功率k_∞的行为和反应堆的燃耗值已通过全功率运行追求了≥12年。对于这些选定的燃料成分,反应堆临界度始于k_∞= 1.4443、1.4872和1.5238,其中相应的反应堆运行时间和燃耗值经计算为2.8年,8年和12.5年以及62,430 MW.D / MT, 176,000和280,000 MW.D / MT,燃料消耗率分别约为16、5.68和3.57 g / MW.D。这些高燃尽将大大减少单位能量输出中的核废料量。该研究清楚地表明,以TRISO燃料颗粒形式存在的TRU将为CANDU反应堆提供足够的临界度以及合理的燃耗,以证明将其视为替代燃料是合理的。

著录项

  • 来源
    《Progress in Nuclear Energy》 |2012年第2012期|p.19-26|共8页
  • 作者单位

    Atihm University, Faculty of Engineering, 06836 incek Golbasi. Ankara, Turkiye;

    Pakistan Institute of Engineering and Applied Sciences, Islamabad 45650, Pakistan,Faculty of Technology, Cazi University, Besevler, Ankara, Turkiye;

    Pakistan Institute of Engineering and Applied Sciences, Islamabad 45650, Pakistan,Faculty of Technology, Cazi University, Besevler, Ankara, Turkiye;

  • 收录信息 美国《科学引文索引》(SCI);美国《工程索引》(EI);
  • 原文格式 PDF
  • 正文语种 eng
  • 中图分类
  • 关键词

    CANDU; TRISO; trans uranium; minor actinides; plutonium; natural uranium;

    机译:坎杜;TRISO;反铀次act系元素;天然铀;

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