DESIGN AND FABRICATION OF REACTOR PRESSURE VESSEL FOR HIGH TEMPERATURE ENGINEERING TEST REACTOR (HTTR)

机译：高温工程试验反应器（HTTR）反应器压力容器的设计与制造

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The reactor pressure vessel (RPV) of the HTTR is 5.5 m in inside diameter, 13.2 m in inside height, and 122 mm and 160 mm in wall thickness of the body and the top head dome, respectively. Because the reactor inlet temperature of the HTTR is higher than that of LWRs, 2 l/4Cr-1Mo steel is chosen for the RPV material. Fluence of the RPV is estimated to be less than 1x10~(17) n/cm~2 (E > 1 MeV), and so irradiation embrittlement is presumed to be negligible, but temper embrittlement is not. For the purpose of reducing embrittlement, content of some elements is limited on 2 1/4 Cr-1 Mo steel for the RPV using embrittlement parameters, J-factor and X . In this paper design, fabrication procedure, and in-service inspection technique of the RPV for the HTTR are described.

机译：HTTR的反应堆压力容器（RPV）的内径为5.5 m，内高度为13.2 m，主体和顶盖圆顶的壁厚分别为122 mm和160 mm。由于HTTR的反应器入口温度高于LWR的反应器入口温度，因此选择2 l / 4Cr-1Mo钢作为RPV材料。 RPV的注量估计小于1x10〜（17）n / cm〜2（E> 1 MeV），因此可以认为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，使用脆化参数，J因子和X将某些元素的含量限制在RPV的2 1/4 Cr-1 Mo钢中。在本文中，描述了用于HTTR的RPV的设计，制造过程和在役检查技术。

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来源
《ASME(American Society of Mechanical Engineers)/JSME Pressure Vessels and Piping Conference: Elevated Temperature Design and Analysis, Nonlinear Analysis, and Plastic Components; 20040725-20040729; San Diego,CA; US》|2004年|P.39-44|共6页
会议地点 San Diego CA(US)
作者
Yukio Tachibana; Shigeaki Nakagawa;
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作者单位

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

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会议组织
原文格式 PDF
正文语种 eng
中图分类机械制造工艺;
关键词
HTGR; HTTR; reactor pressure vessel; 2 l/4Cr-1Mo steel; embrittlementl in-service inspection;

机译：HTGR; HTTR;反应堆压力容器; 2 l / 4Cr-1Mo钢; embrittlementl在役检查;

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1. Design of the reactor internals of the high temperature engineering test reactor(HTTR) [J] . N. Tsuji, K. Jinza, S. Funaguchi 富士時報 . 1998,第4期

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2. Design of the reactor internals of the high temperature engineering test reactor(HTTR) [J] . N. Tsuji, K. Jinza, S. Funaguchi 富士時報 . 1998,第4期

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3. Reactor pressure vessel design of the high temperature engineering test reactor [J] . Yukio Tachibana, Shigeaki Nakagawa, Tatsuo Iyoku Nuclear Engineering and Design . 2004,第1a3期

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4. LOSS OF CORE COOLING TEST WITHOUT ONE COOLING LINE IN VESSEL COOLING SYSTEM (VCS) OF HIGH TEMPERATURE ENGINEERING TEST REACTOR (HTTR) [C] . Yusuke FUJIWARA, Daisuke TOCHIO, Shimpei HAMAMOTO, International conference on nuclear engineering . 2016

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6. On the Elevated Temperature Thermal Stability of Nanoscale Mn-Ni-Si Precipitates Formed at Lower Temperature in Highly Irradiated Reactor Pressure Vessel Steels [O] . N. Almirall, P. B. Wells, H. Ke, -1

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DESIGN AND FABRICATION OF REACTOR PRESSURE VESSEL FOR HIGH TEMPERATURE ENGINEERING TEST REACTOR (HTTR)

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