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Benchmark Evaluation of Start-Up and Zero-Power Measurements at the High-Temperature Engineering Test Reactor

机译:高温工程测试反应堆的启动和零功率测量的基准评估

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摘要

Benchmark models were developed to evaluate six cold-critical and two warm-critical, zero-power measurements of the high-temperature engineering test reactor (HTTR). Additional measurements of the subcritical configuration of the fully loaded core, core excess reactivity, shutdown margins, six isothermal temperature coefficients, and axial reaction-rate distributions were also evaluated as acceptable benchmark experiments. Insufficient information is publicly available to develop finely detailed models of the HTTR as much of the design information is still proprietary. The uncertainties in the benchmark models are judged to be of sufficient magnitude to encompass any biases and bias uncertainties incurred through the simplification process used to develop the benchmark models. However, use of the benchmark critical configurations of the HTTR for nuclear data adjustment is not recommended as the impact of these biases has not been addressed with rigorous detail. The impact of any simplification biases, if any, is not expected to significantly impact evaluation of the other reactor physics measurement calculations. Dominant uncertainties in the experimental k_(eff) for all core configurations come from uncertainties in the impurity content of the various graphite blocks that compose the HTTR. Monte Carlo calculations of k_(eff) are between ~0.9% and ~2.7% greater than the benchmark values. Reevaluation of the HTTR models as additional information becomes available could improve the quality of this benchmark and possibly reduce the computational biases. High-quality characterization of graphite impurities would significantly improve the quality of the HTTR benchmark assessment. Simulations of the other reactor physics measurements are in good agreement with the benchmark experiment values. The complete benchmark evaluation details are available in the 2014 edition of the International Handbook of Evaluated Reactor Physics Benchmark Experiments.
机译:开发了基准模型,以评估高温工程测试反应堆(HTTR)的六个冷临界和两个暖临界零功率测量。还评估了满负荷堆芯的亚临界构型,堆芯过量反应性,关闭裕度,六个等温温度系数和轴向反应速率分布的其他测量结果,作为可接受的基准实验。由于许多设计信息仍然是专有的,因此公开提供的信息不足,无法开发HTTR的精细模型。基准模型中的不确定性被判断为足够大,足以涵盖由于用于开发基准模型的简化过程而产生的任何偏差和偏差不确定性。但是,不建议将HTTR的基准关键配置用于核数据调整,因为这些偏见的影响尚未得到严格的解决。任何简化偏差的影响(如果有的话)都不会显着影响其他反应堆物理测量计算的评估。所有核结构的实验k_(eff)的主要不确定性来自构成HTTR的各种石墨块的杂质含量的不确定性。 k_(eff)的蒙特卡洛计算值比基准值高约0.9%至2.7%。随着可获得更多信息,对HTTR模型进行重新评估可以提高该基准的质量,并可能减少计算偏差。石墨杂质的高质量表征将显着提高HTTR基准评估的质量。其他反应堆物理测量的模拟与基准实验值非常吻合。完整的基准评估详细信息可在2014年版的《反应堆物理基准实验国际手册》中获得。

著录项

  • 来源
    《Nuclear science and engineering》 |2014年第3期|414-427|共14页
  • 作者

    John D. Bess; Nozomu Fujimoto;

  • 作者单位

    Idaho National Laboratory P.O. Box 1625, MS 3855, Idaho Falls, Idaho 83415;

    Japan Atomic Energy Agency, Department of HTTR, Oarai Research and Development Center 4002 Narita-Cho, Oarai-machi, Higashiibaraki-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
  • 关键词

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