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Shifting study of a VHTR using reprocessed fuel with various TRISO packing fractions

机译:使用具有不同TRISO填充分数的后处理燃料的VHTR的转换研究

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摘要

A simplified VHTR (very high temperature reactor) loaded with a mixture of depleted uranium and transuranics (TRUs) fuel was analyzed changing the TRISO packing fraction (pf), i.e., the TRISO kernel radius. Five cases were simulated and evaluated during 900 days with a burnup of 92,700.0 MWD/THM without reloads. The effective multiplication factor (k_(eff)) and the fast/thermal flux ratio at zero and full power, fuel temperature coefficient (α_(TF)). moderator temperature coefficient (α_(TM)), and fuel composition at BOL (begin of life) and EOL (end of life) were analyzed. Overall, the results show that transuranics elements from reprocessed fuel of PWRs spiked with depleted uranium (0.2% ~(235)U) to obtain 15% LEU-fuel (~(235)U, ~(239)Pu and ~(241)Pu) can be used as fuel in VHTR. The calculations were carried out with the Winfrith Improved Multi-Group Scheme (WIMSD5) code and the ENDFB65 cross-section data (Askew et al., 1966; Leszczynski, 1990).
机译:分析了装有贫铀和超铀酸(TRUs)燃料混合物的简化VHTR(超高温反应堆),它改变了TRISO的填充率(pf),即TRISO核半径。在900天内模拟和评估了5个案例,没有重新加载就消耗了92,700.0 MWD / THM。有效乘数(k_(eff))以及零功率和全功率下的快速/热通量比,燃料温度系数(α_(TF))。分析了慢化剂温度系数(α_TM),以及BOL(寿命开始)和EOL(寿命终止)时的燃料成分。总体而言,结果表明,来自加注了贫铀(0.2%〜(235)U)的压水堆的后处理燃料中的超铀元素,可获得15%的LEU燃料(〜(235)U,〜(239)Pu和〜(241) Pu)可用作VHTR的燃料。使用Winfrith改进多组方案(WIMSD5)代码和ENDFB65横截面数据进行了计算(Askew等,1966; Leszczynski,1990)。

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  • 来源
    《Nuclear Engineering and Design》 |2012年第7期|p.42-47|共6页
  • 作者单位

    Departamento de Engenharia Nuclear, Universidade Federal de Minos Cerais, Av. Antonio Carlos, 6627 - Campus UFMG, PCA1 - Anexo Engenharia - Pampulha, CEP 31270-901,Belo Horizonte, MG, Brazil,Instituto Nacional de Ciencias e Tecnologia de Reatores Nudeares Inovadores/CNPq, Brazil;

    Departamento de Engenharia Nuclear, Universidade Federal de Minos Cerais, Av. Antonio Carlos, 6627 - Campus UFMG, PCA1 - Anexo Engenharia - Pampulha, CEP 31270-901,Belo Horizonte, MG, Brazil,Instituto Nacional de Ciencias e Tecnologia de Reatores Nudeares Inovadores/CNPq, Brazil;

    Departamento de Engenharia Nuclear, Universidade Federal de Minos Cerais, Av. Antonio Carlos, 6627 - Campus UFMG, PCA1 - Anexo Engenharia - Pampulha, CEP 31270-901,Belo Horizonte, MG, Brazil,Instituto Nacional de Ciencias e Tecnologia de Reatores Nudeares Inovadores/CNPq, Brazil;

    Departamento de Engenharia Nuclear, Universidade Federal de Minos Cerais, Av. Antonio Carlos, 6627 - Campus UFMG, PCA1 - Anexo Engenharia - Pampulha, CEP 31270-901,Belo Horizonte, MG, Brazil,Instituto Nacional de Ciencias e Tecnologia de Reatores Nudeares Inovadores/CNPq, Brazil;

  • 收录信息 美国《科学引文索引》(SCI);美国《工程索引》(EI);美国《生物学医学文摘》(MEDLINE);
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  • 正文语种 eng
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