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Reevaluation of Experimental Data and Analysis on Experimental Fast Reactor JOYO MK-I Performance Tests

机译:实验数据的重新评估和快速反应堆JOYO MK-I性能测试的分析

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摘要

Experimental data acquired during experimental fast reactor JOYO MK-I performance tests in the late 1970s have been reevaluated and analyzed with a nuclear analysis system for fast reactors employed by the Japan Atomic Energy Agency. For the purpose of improving the prediction accuracy of nuclear characteristics, nominal values and uncertainties of the experimental data were reevaluated in light of knowledge obtained after the MK-I performance test and calculation results based on the latest reactor physics analysis methods. All nominal values were corrected by a formulation of control rod interaction effects proposed in the present paper, and all possible uncertainty factors were evaluated and quantified.rnThe analysis results agreed well with measured values within the experimental and nuclear-induced uncertainties for all the nuclear characteristics of criticality, control rod worth, sodium void reactivity, fuel replacement reactivity, and isothermal temperature coefficient.rnMeanwhile, the present reevaluated data have been registered with the International Reactor Physics Benchmark Experiments Project with the expectation that these data will be widely used.
机译:在1970年代后期进行的实验性快堆JOYO MK-I性能测试中获得的实验数据已经重新评估并通过日本原子能机构采用的用于快堆的核分析系统进行了分析。为了提高核特性的预测准确度,根据MK-I性能测试和基于最新反应堆物理分析方法的计算结果,对实验数据的标称值和不确定性进行了重新评估。通过本文提出的控制棒相互作用效应公式校正了所有标称值,并对所有可能的不确定性因素进行了评估和量化。rn分析结果与所有核特性在实验和核致不确定性范围内的测量值吻合得很好。同时,目前重新评估的数据已在国际反应堆物理基准实验项目中注册,期望这些数据将被广泛使用。

著录项

  • 来源
    《Nuclear science and engineering》 |2007年第3期|249-263|共15页
  • 作者单位

    Advanced Nuclear System Research and Development Directorate, Japan Atomic Energy Agency 4002, Narita-cho, O-arai-machi, Higashi-Ibaraki-gun, Ibaraki 311-1393, Japan;

  • 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 原子能技术;
  • 关键词

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