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Measurement of mechanical properties of a reactor operated Zr-2.5Nb pressure tube using an in situ cyclic ball indentation system

机译:使用原位循环球压痕系统测量反应堆操作的Zr-2.5Nb压力管的机械性能

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Periodic measurement of mechanical properties of pressure tubes of Indian Pressurised Heavy Water Reactors is required for assessment of their fitness for continued operation. Removal of pressure tube from the core for preparation of specimens to test for mechanical properties in laboratories consumes large amounts of radiation and hence is to be avoided as far as possible. In the field of in situ estimation of properties of materials, cyclic ball indentation is an emerging technique. Presently, commercial systems are available for doing indentation test either on outside surface of a component at site or on a test piece in a laboratory. However, these systems cannot be used inside a pressure tube for carrying out ball indentation trials under in situ condition. Considering this, a remotely operable hydraulic In situ Property Measurement System (IProMS) based on cyclic ball indentation technique has been designed and developed in house. The tool head of IProMS can be located inside a pressure tube at any axial location under in situ condition and the properties can be estimated from an analysis of the data on load and depth of indentation, recorded during the test. In order to qualify the system, a number of experimental trials have been conducted on spool pieces and specimens prepared from Zr-2.5Nb pressure tube having different mechanical properties. Based on the encouraging results obtained from the qualification trials, IProMS has been used inside a reactor operated pressure tube which has been removed from Kakrapar Atomic Power Station-2 after 12.76 Full Power Years of operation for post irradiation examination studies at Bhabha Atomic Research Centre. This paper highlights the basic theory of measurement, results from the qualification trials on Zr-2.5Nb material having different mechanical properties and reactor operated irradiated pressure tube. (C) 2015 Elsevier B.V. All rights reserved.
机译:需要定期测量印度加压重水反应堆压力管的机械性能,以评估其能否继续运行。从岩心上取下压力管以制备样品以测试实验室的机械性能会消耗大量辐射,因此应尽可能避免。在原位估计材料特性的领域中,循环球压痕是一种新兴的技术。当前,商业系统可用于在现场在部件的外表面上或在实验室的测试件上进行压痕测试。但是,这些系统不能在压力管内用于在原位条件下进行球压痕试验。考虑到这一点,在室内设计并开发了一种基于循环球压痕技术的可远程操作的液压现场特性测量系统(IProMS)。 IProMS的工具头可以在原位条件下位于任何轴向位置的压力管内,并且可以通过对在测试期间记录的载荷和压痕深度的数据进行分析来评估其性能。为了使该系统合格,已对由具有不同机械性能的Zr-2.5Nb压力管制备的线轴件和样品进行了许多试验。基于从资格试验中获得的令人鼓舞的结果,已在反应堆操作的压力管内使用了IProMS,该压力管在满负荷运行12.76满功率年后已从Kakrapar原子能发电站2拆除,用于Bhabha原子研究中心的辐射后检查研究。本文着重介绍了测量的基本理论,是对具有不同机械性能的Zr-2.5Nb材料和反应堆操作的辐照压力管进行的鉴定试验的结果。 (C)2015 Elsevier B.V.保留所有权利。

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  • 来源
    《Nuclear Engineering and Design》 |2015年第7期|19-26|共8页
  • 作者单位

    Bhabha Atom Res Ctr, Reactor Engn Div, Bombay 400085, Maharashtra, India;

    Bhabha Atom Res Ctr, Reactor Engn Div, Bombay 400085, Maharashtra, India;

    Bhabha Atom Res Ctr, Reactor Engn Div, Bombay 400085, Maharashtra, India;

  • 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
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