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Postirradiation Testing of High Temperature Reactor Spherical Fuel Elements Under Accident Conditions

机译:事故条件下高温反应堆球形燃料元件的辐照后测试

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摘要

A new furnace for accident condition testing of spherical high temperature reactor fuel elements has been installed and now operates in the hot cells of the Institute for Transuranium Elements (ITU) Karlsruhe. The recent apparatus was constructed on the basis of a former development by Forschungszentrum Juelich (Schenk, Pitzer, and Nabielek, 1988, "Fission Product Release Profiles From Spherical HTR Fuel Elements at Accident Temperatures," Jillich Report No. 2234), where it was named KueFA, the German acronym for cold finger apparatus. In a preceding publication (Kostecka, Ejton, de Weerd, and Toscano, 2004, "Post-Irradiation Testing of HTR-Fuel Elements Under Accident Conditions, Part 1 and 2," Second International Topical Meeting on High Temperature Reactor Technology, Beijing, China) the general concept and details of the device were described. The present paper reports on the first operation under hot conditions, and the calibration of the fission gas measurement and of the efficiency of the cold finger, which is used to plate out solid fission products. Finally the results of fission product release and analysis of two heating tests on two fuel elements from the high temperature reactor K6 irradiation experiment (Nabielek, Conrad, Roellig, and Meyers, 1993, "Fuel Irradiation Experiments on HFR-K6 and HFR-B1 With Intermittent Water Vapour Injections," Technical Committee Meeting on Response of Fuel, Fuel Elements and Gas Cooled Reactor Cores Under Accidental Air or Water Ingress Conditions, Beijing, China, Oct. 25-27) are presented and discussed.
机译:已安装了用于球形高温反应堆燃料元件事故条件测试的新炉,该炉现在在卡尔斯鲁厄超铀元素研究所(ITU)的热室中运行。最近的设备是在Forschungszentrum Juelich(Schenk,Pitzer和Nabielek,1988年,“事故温度下球形HTR燃料元件的裂变产物释放曲线”,Jillich报告第2234号)的先前开发成果的基础上构造而成的。名为KueFA,德国冷手指仪的首字母缩写。在先前的出版物(Kostecka,Ejton,de Weerd和Toscano,2004年,“事故条件下HTR燃料元素的辐照后测试,第1和第2部分”,第二次高温反应堆技术国际专题会议,北京,中国)描述了设备的一般概念和细节。本文报道了在高温条件下的第一个操作,以及裂变气体测量和冷指效率的标定,该方法用于沉积固体裂变产物。最后,从高温反应堆K6辐照实验(Nabielek,Conrad,Roellig和Meyers,1993年,“对HFR-K6和HFR-B1进行的燃料辐照实验” “间歇性水蒸气喷射”,关于在偶然的空气或水进入条件下燃料,燃料元件和气冷反应堆堆芯响应的技术委员会会议,中国北京,10月25日至27日)进行了讨论。

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  • 来源
    《Journal of Engineering for Gas Turbines and Power》 |2010年第4期|042901.1-042904.6|共6页
  • 作者单位

    Institute for Transuranium Elements, European Commission-Joint Research Centre, Postfach 2340, Karlsruhe 76344, Germany;

    Institute for Transuranium Elements, European Commission-Joint Research Centre, Postfach 2340, Karlsruhe 76344, Germany;

    Institute for Transuranium Elements, European Commission-Joint Research Centre, Postfach 2340, Karlsruhe 76344, Germany;

    Institute for Transuranium Elements, European Commission-Joint Research Centre, Postfach 2340, Karlsruhe 76344, Germany;

    Institute for Transuranium Elements, European Commission-Joint Research Centre, Postfach 2340, Karlsruhe 76344, Germany;

    Institute for Transuranium Elements, European Commission-Joint Research Centre, Postfach 2340, Karlsruhe 76344, Germany;

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