首页> 外文会议>The 13th Pacific Basin Nuclear Conference: Abstracts Oct 21-25, 2002 Shenzhen, China >SHIELDING BENCHMARK EXPERIMENT FOR SPENT FUEL DRY STORAGE FACILITY
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SHIELDING BENCHMARK EXPERIMENT FOR SPENT FUEL DRY STORAGE FACILITY

机译:燃料干储存设施的烫印基准实验

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摘要

The large-scale interim spent fuel dry storage facilities from nuclear power plants are plannedrnto start operation by 2010 in Japan. The requirements of these facilities are a big spent fuelrnstorage capacity and a restricted site usage close to the boundary. These cause a strong requestrnof precise and realistic dose estimation for licensing procedure. To resolve this difficulty threerndimensional Monte Carlo calculation methods are introduced, which is always requested torncompare the benchmark experiment of the shielding system for the verification of procedurernand statistical errors. Here, two kinds of shielding benchmark experiments; the huge ductrnstreaming and the cask shadow shielding experiments, were newly prepared to get thesernabsent data.rnAs a first step, the huge duct streaming experiment is outlined and the obtained results arerndiscussed. Neutron and gamma flux and dose distributions in and around the streaming ductrnwere measured by moderating type neutron detectors, neutron dosimeters, activation foils,rnsolid state track detectors (CR-39), thermoluminescent dosimeters, glass dosimeters, etc.rnThese results are also compared with the Monte Carlo calculations. Through these proceduresrnthe know-how of the spatial dose estimation in and around a huge streaming duct werernobtained.
机译:计划在2010年之前在日本启动核电站的大型临时乏燃料干燥存储设施。这些设施的需求是大的乏燃料存储能力以及靠近边界的受限场地使用。这些引起了对许可程序的精确而现实的剂量估计的强烈要求。为了解决这一难题,提出了三维蒙特卡罗计算方法,该方法总是要求对屏蔽系统的基准实验进行比较,以验证程序和统计误差。这里,有两种屏蔽基准实验;为获得有效的数据,重新准备了巨大的管道流和木桶遮蔽实验。第一步,概述了巨大的管道流实验,并讨论所获得的结果。通过调节型中子探测器,中子剂量计,活化箔,固态轨道探测器(CR-39),热发光剂量计,玻璃剂量计等测量了流道内和周围流道中的中子和伽马通量及剂量分布。蒙特卡洛计算。通过这些程序,获得了在巨大的流道内和周围的空间剂量估算的专门知识。

著录项

  • 来源
  • 会议地点 Shenzhen(CN);Shenzhen(CN)
  • 作者单位

    Research Center for Nuclear Science and Technology, The University of Tokyo, Japan;

    Research Center for Nuclear Science and Technology, The University of Tokyo, Japan;

    Nuclear Power Engineering Department, Tokyo Electric Power Company, Japan;

    Domestic Project Division, Toyo Engineering Corporation, Japan;

    Domestic Project Division, Toyo Engineering Corporation, Japan;

    Energy Engineering Department, CRC Solutions Corporation, Japan;

    Nuclear Fuel Cycle Project Department, Ishikawajima-Harima Heavy Industries Co., Ltd., Japan;

    State Research and Development Center for Expertises of Projects and Technologies, Ministry for Atomic Energy, Russia;

    Scientific Association for Physics, Computer Data, Technology, Russia;

    Radiation Research Division, Russian State Scientific Center Institute for High Energy Physics, Russia;

    Radiation Research Division, Russian State Scientific Center Institute for High Energy Physics, Russia;

    Radiation Research Division, Russian State Scientific Center Institute for High Energy Physics, Russia;

  • 会议组织
  • 原文格式 PDF
  • 正文语种 eng
  • 中图分类 核能工业 ;
  • 关键词

    shielding; benchmark experiment; spent fuel dry storage; monte carlo method; MCNP;

    机译:屏蔽;基准测试;乏燃料干燥存储;蒙特卡洛法; MCNP;

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