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首页> 外文期刊>Nuclear fusion >A study of ~(239)Pu production rate in a water cooled natural uranium blanket mock-up of a fusion-fission hybrid reactor
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A study of ~(239)Pu production rate in a water cooled natural uranium blanket mock-up of a fusion-fission hybrid reactor

机译：聚变裂变混合堆水冷天然铀层模型中〜（239）Pu产率的研究

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摘要

The ~(239)Pu production rate is important data in neutronics design for a natural uranium blanket of a fusion-fission hybrid reactor, and the accuracy and reliability should be validated by integral experiments. The distribution of ~(239)Pu production rates in a subcritical natural uranium blanket mock-up was obtained for the first time with a D-T neutron generator by using an activation technique. Natural uranium foils were placed in different spatial locations of the mock-up, the counts of 277.6 keV γ-rays emitted from ~(239)Np generated by ~(238)U capture reaction were measured by an HPGe γ spectrometer, and the self-absorption of natural uranium foils was corrected. The experiment was analyzed using the Super Monte Carlo neutron transport code SuperMC2.0 with recent nuclear data of ~(238)U from the ENDF/ B-Ⅶ.0, ENDF/B-Ⅶ.1, JENDL-4.0u2, JEFF-3.2 and CENDL-3.1 libraries. Calculation results with the JEFF-3.2 library agree with the experimental ones best, and they agree within the experimental uncertainty in general with the average ratios of calculation results to experimental results (C/E) in the range of 0.93 to 1.01.
机译：〜（239）Pu的生成率是聚变裂变混合堆天然铀覆盖层中子学设计的重要数据，其准确性和可靠性应通过整体实验加以验证。使用活化技术，使用D-T中子发生器首次获得了亚临界天然铀层模型中〜（239）Pu生产率的分布。将天然铀箔放在模型的不同空间位置，用HPGeγ光谱仪测量〜（238）U捕获反应产生的〜（239）Np发出的277.6 keVγ射线的计数，校正了天然铀箔的吸收。使用超级蒙特卡洛中子输运代码SuperMC2.0分析了该实验，并从ENDF /B-Ⅶ.0，ENDF /B-Ⅶ.1，JENDL-4.0u2，JEFF- 3.2和CENDL-3.1库。 JEFF-3.2库的计算结果与实验结果最佳吻合，并且它们在实验不确定性范围内通常与计算结果与实验结果的平均比率（C / E）在0.93至1.01的范围内一致。

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  • 来源
    《Nuclear fusion》 |2016年第3期|036019.1-036019.9|共9页
  • 作者

    Song Feng; Rong Liu; Xinxin Lu; Yiwei Yang; Kun Xu; Mei Wang; Tonghua Zhu; Li Jiang; Jianguo Qin; Jieqiong Jiang; Zijie Han; Caifeng Lai; Zhongwei Wen;

  • 作者单位

    Institute of Nuclear Physics and Chemistry, China Academy of Engineering Physics, Mianyang 621900, People's Republic of China,Key Laboratory of Neutronics and Radiation Safety, Institute of Nuclear Energy Safety Technology, Chinese Academy of Sciences, Hefei 230031, People's Republic of China,Dipartimento di Fisica 'G Occhialini', Universita degli Studi di Milano-Bicocca, Milano 20126, Italy;

    Institute of Nuclear Physics and Chemistry, China Academy of Engineering Physics, Mianyang 621900, People's Republic of China,Key Laboratory of Neutron Physics, China Academy of Engineering Physics, Mianyang 621900, People's Republic of China;

    Institute of Nuclear Physics and Chemistry, China Academy of Engineering Physics, Mianyang 621900, People's Republic of China;

    Institute of Nuclear Physics and Chemistry, China Academy of Engineering Physics, Mianyang 621900, People's Republic of China;

    School of Nuclear Science and Technology, University of Science and Technology of China, Hefei 230026, People's Republic of China;

    Institute of Nuclear Physics and Chemistry, China Academy of Engineering Physics, Mianyang 621900, People's Republic of China;

    Institute of Nuclear Physics and Chemistry, China Academy of Engineering Physics, Mianyang 621900, People's Republic of China;

    Institute of Nuclear Physics and Chemistry, China Academy of Engineering Physics, Mianyang 621900, People's Republic of China;

    Institute of Nuclear Physics and Chemistry, China Academy of Engineering Physics, Mianyang 621900, People's Republic of China;

    Key Laboratory of Neutronics and Radiation Safety, Institute of Nuclear Energy Safety Technology, Chinese Academy of Sciences, Hefei 230031, People's Republic of China;

    Institute of Nuclear Physics and Chemistry, China Academy of Engineering Physics, Mianyang 621900, People's Republic of China;

    Institute of Nuclear Physics and Chemistry, China Academy of Engineering Physics, Mianyang 621900, People's Republic of China;

    Institute of Nuclear Physics and Chemistry, China Academy of Engineering Physics, Mianyang 621900, People's Republic of China;

  • 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);
  • 原文格式 PDF
  • 正文语种 eng
  • 中图分类
  • 关键词

    D-T neutrons; ~(239)Pu production rate; natural uranium blanket mock-up; integral neutronics experiment;

    机译：D-T中子;〜（239）Pu生产率;天然铀毯模型积分中子实验;

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