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首页> 外文期刊>International journal of energy research >Neutronic performance of CANDU reactor fuelling with ThC_2/~(233)UC_2
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Neutronic performance of CANDU reactor fuelling with ThC_2/~(233)UC_2

机译:ThC_2 /〜(233)UC_2为CANDU反应堆供能的中子性能

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摘要

~(233)U isotope is used as a booster fissile fuel material in the form of mixed ThC_2/~(233)UC_2 fuel in a Canada Deuterium Uranium (CANDU) fuel bundle in order to assure the initial criticality at startup. Three different fuel compositions have been used: (1) 97% ThC_2+3% ~(233)UC_2, (2) 98% ThC_2+2% ~(233)UC_2 and (3) 99% ThC_2+l% ~(233)UC_2. The temporal variation of the criticality K_∞ and the burn-up values of the reactor have been calculated by full-power operation for a period of 20 years. The criticality starts by k_∞ = 1.541, 1.355 and 0.995 for modes of (1), (2) and (3) fuel compositions, respectively. A sharp decrease in the criticality has been observed in the first 2 years as a consequence of rapid ~(233)U burnout fuelling with (1) and (2) modes. The criticality becomes quasi-constant after the second year and remains above K_∞ 1.06 for 20 years. After the second year, the CANDU reactor begins to operate practically as a thorium burner. Very high burnup could be achieved with the same fuel materials (up to 500000 MWdayt~(-1)), provided that the fuel rod claddings would be replaced periodically (after every 50000 or 100000 MWdayt~(-1)). The reactor criticality will be sufficient for fuelling with (1) and (2) modes until a great fraction of the thorium fuel is burnt up. This would reduce fuel fabrication costs and nuclear waste mass for final disposal per unit energy drastically.
机译:〜(233)U同位素以加拿大氘铀(CANDU)燃料束中的混合ThC_2 /〜(233)UC_2燃料的形式用作增强易裂变燃料材料,以确保启动时的初始临界性。已经使用了三种不同的燃料成分:(1)97%ThC_2 + 3%〜(233)UC_2,(2)98%ThC_2 + 2%〜(233)UC_2和(3)99%ThC_2 + 1%〜(233 )UC_2。临界K_∞的时间变化和反应堆的燃尽值已通过满功率运行了20年进行了计算。对于(1),(2)和(3)燃料成分的模式,临界度分别由k_∞= 1.541、1.355和0.995开始。在前两年中,由于在(1)和(2)模式下快速〜(233)U燃尽燃料,已发现临界值急剧下降。临界度在第二年后变得准恒定,并在20年内保持在K_∞1.06以上。第二年之后,CANDU反应堆实际上开始用作a燃烧器。如果燃料棒包壳要定期更换(每50000 MWdayt〜(-1)之后),则使用相同的燃料材料(高达500000 MWdayt〜(-1))可以实现非常高的燃耗。反应堆的临界值足以在(1)和(2)模式下供油,直到大部分or燃料燃烧完毕。这将大大降低单位最终能源的最终燃料制造成本和核废料量。

著录项

  • 来源
    《International journal of energy research》 |2011年第2期|p.103-111|共9页
  • 作者单位

    Engineering Faculty, Department of Mechanical Engineering, Aksaray University, Aksaray, Turkey;

    Engineering Faculty, Department of Mechanical Engineering, Aksaray University, Aksaray, Turkey;

    Engineering Faculty, Department of Mechanical Engineering, Nigde University, Nigde, Turkey;

  • 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; thorium; uranium; criticality; burnup;

    机译:坎杜;钍;铀;关键性耗尽了;

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