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Reactor pressure vessel design of the high temperature engineering test reactor

机译:高温工程试验堆的反应堆压力容器设计

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摘要

The reactor pressure vessel (RPV) of the HTTR is 5.5 m (inside diameter), 13.2 m (inside height), and 122 mm (shell thickness). The RPV contains core components, reactor internals, reactivity control system, etc. 21/4Cr-1Mo steel is chosen as the material for RPV. The temperature reaches about 400℃ at normal operation. The fluence of the RPV is estimated to be less than 1 x 10~(17) n/cm~2 (E > 1 MeV) and so irradiation embrittlement is negligible, but temper embrittlement is not negligible. For the purpose of reducing embrittlement, content of some elements must be limited in the 21/4Cr-1Mo steel for the RPV; embrittlement parameters, J-factor and X are used. In this paper, design and structure of the RPV are reviewed first. Fabrication procedure of the RPV and its special feature are described. Material data on the 21/4Cr-1Mo steel manufactured for the RPV, especially the embrittlement parameters, J-factor and X, and nil-ductility transition temperatures, T_(NDT), by drop weight tests, are shown. In-service inspection and results of R&Ds are also described.
机译:HTTR的反应堆压力容器(RPV)为5.5 m(内直径),13.2 m(内高度)和122 mm(壳厚度)。 RPV包含核心组件,反应器内部组件,反应性控制系统等。选择21 / 4Cr-1Mo钢作为RPV的材料。正常运行时温度达到约400℃。 RPV的注量估计小于1 x 10〜(17)n / cm〜2(E> 1 MeV),因此辐照脆化可以忽略不计,而回火脆化则可以忽略不计。为了减少脆化,必须限制RPV的21 / 4Cr-1Mo钢中某些元素的含量。使用脆化参数,J因子和X。本文首先对RPV的设计和结构进行了综述。描述了RPV的制造过程及其特殊功能。通过落锤测试显示了为RPV生产的21 / 4Cr-1Mo钢的材料数据,特别是脆性参数J因子和X以及零延性转变温度T_(NDT)。还描述了在役检查和R&D的结果。

著录项

  • 来源
    《Nuclear Engineering and Design》 |2004年第3期|p.103-112|共10页
  • 作者单位

    Department of HTTR Project, Oarai Research Establishment, Japan Atomic Energy Research Institute, Oarai-machi, Ibaraki 311-1394, 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

  • 入库时间 2022-08-18 00:48:17

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