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第12回
高温機器モニタリングを目指した高温用電磁超音波 プローブの開発と評価
著者:
内一 哲哉,Tetsuya UCHIMOTO,高木 敏行,Toshiyuki TAKAGI,尾形 翔平,Shohei OGATA,Gerd DOBMANN
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Abstract: An electromagnetic acoustic transducer (EMAT) design using an air-cored solenoid coil as a pulsed electromagnet is proposed for high-temperature non-contact monitoring, and prototype probe is evaluated through performance test in the range from room temperature to 700°C. The coil generates a biasing magnetic field that enables the device to overcome the Curie temperature limitations of conventional EMATs. Pulsed echo measurements of carbon steel are performed at high temperatures, and verify ...
英字タイトル:
Development and Evaluation of High Temperature EMAT Aiming at Monitoring of High Temperature Components
第12回
高温用薄膜UTセンサを用いた配管減肉のモニタリング
著者:
鶴田 孝義,Takayoshi TSURUTA,小平 武志,Takeshi KODAIRA,山本 裕子,Yuko YAMAMOTO,関 伊佐夫,Isao SEKI,松浦 貴之,Takayuki MATSUURA
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As for periodical measurement of pipe wall thinning, several concerns are indicated, such as unstability of measurement position and contact condition, additional work for removal of insulating material and preparing scaffold, unstability on complex geometry and difficulty of continuous monitoring under plant operation. In order to solve these concerns, we developed thin-film UT sensor which has high-temperature durability and flexibility. Furthermore, we preliminary developed prototype linear phased-a...
英字タイトル:
Monitoring of pipe wall thinning using high-temperature thin-film UT sensor
第12回
高温高圧希釈人工海水中におけるSUS304 鋼の隙間腐食挙動に及ぼすγ線照射の影響
著者:
橘 正彦,Masahiko TACHIBANA,石田 一成,Kazushige ISHIDA,和田 陽一,Yoichi WADA,清水 亮介,Ryosuke SHIMIZU,太田 信之,Nobuyuki OTA,茂中 尚登,Naoto SHIGENAKA,会沢 元浩,Motohiro AIZAWA
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In order to confirm the effects of gamma-ray irradiation on crevice corrosion behavior of type 304 stainless steel (304 SS), the repassivation potential was experimentally examined in high temperature test seawater (simulated diluted seawater) under gamma-ray irradiation in diluted artificial seawater at temperatures from 323 to 553 K, in conformity to Japanese Industrial Standards (JIS) G 0592. Overall, for high temperatures from 373 to 553 K, the repassivation potentials decreased with increasing chl...
英字タイトル:
Effects of Gamma Ray Irradiation on Crevice Corrosion Behavior of Type 304 Stainless Steel in High Temperature High Pressure Diluted Artificial Seawater.
第12回
高速実験炉「常陽」における原子炉容器内補修技術の開発と実践 - 炉心上部機構の交換 -
著者:
清水 俊二,Shunji SHIMIZU,奥田 英二,Eiji OKUDA,菊池 祐樹,Yuki KIKUCHI,川崎 徹,Toru KAWASAKI,大和田 良平,Ryohei OHWADA
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In the experimental fast reactor “Joyo”, it was confirmed that the top of the irradiation test sub-assembly of “MARICO-2” (material testing rig with temperature control) had been broken and bent onto the in-vessel storage rack as an obstacle and had damaged the upper core structure (UCS). This incident necessitated the replacement of the UCS and the retrieval of the MARICO-2 sub-assembly for “Joyo” restoration. This paper describes the in-vessel repair techniques for UCS replacement, which are develope...
英字タイトル:
Development of repair techniques in the reactor vessel of the experiment fast reactor “Joyo” - Replacement of Upper Core Structure -
第12回
高速実験炉「常陽」における炉内補修技術の開発と実践
著者:
芦田 貴志,Takashi ASHIDA,高松 操,Misao TAKAMATSU,伊東 秀明,Hideaki ITO,大川 敏克,Toshikatsu OHKAWA,吉原 静也,Shizuya YOSHIHARA
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The experimental fast reactor Joyo is the first sodium cooled fast reactor (SFR) that was constructed in Japan. In 2007, it was confirmed that the top of the irradiation test sub-assembly (S/A) of “MARICO-2” (material testing rig with temperature control) had been broken and bent as an obstacle inside of the Joyo reactor vessel and had damaged the upper core structure (UCS). This incident necessitated the replacement of the UCS and the retrieval of the MARICO-2 sub-assembly for Joyo restoration. This p...
第12回
高速実験炉「常陽」における炉内補修技術の開発と実践 - MARICO-2 試料部の回収-
著者:
皆藤 泰昭,Yasuaki KAITO,芦田 貴志,Takashi ASHIDA,今泉 和幸,Kazuyuki IMAIZUMI,伊澤 修,Osamu IZAWA,内藤 裕之,Hiroyuki NAITO
発刊日:
公開日:
キーワードタグ:
In the experimental fast reactor “Joyo”, it was confirmed that the top of the irradiation test sub-assembly (S/A) of “MARICO-2” (material testing rig with temperature control) had been bent onto the in-vessel storage rack as an obstacle, and the MARICO-2 S/A had been stuck in the transfer pot owing to its deformation. Since the MARICO-2 S/A cannot be retrieved with the existing handling equipment, special handling equipment was developed while considering the anomalous conditions. Emphasis had been pla...
英字タイトル:
Development of repair techniques in the reactor vessel of the experimental fast reactor Joyo . Retrieval of the MARICO-2 test subassembly .
第12回
高速炉プラント（「もんじゅ」）の安全性確保の考え方
著者:
岡田 俊親,Toshichika OKADA,市川 健太,Ichikawa KENTA,二神 敏,Futagami SATOSHI,江沼 康弘,Yasuhiro ENUMA,宮川 明,Akira MIYAKAWA,堺 公明,Takaaki SAKAI,中井 良大,Ryodai NAKAI
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Japan Atomic Energy Agency (JAEA) has organized “Pier Review Committee of Monju” consisting of experts on sodium cooled reactors and nuclear safety assessment in order to discuss and propose safety requirements for the prototype FBR Monju. JAEA is now researching the optimum plan in accordance with these safety requirements. Adopting another independent interlocking-system for the back-up shut-down system can reduce the accident risk of ULOHS: unprotected loss of heat sink. The heat transfer system of ...
英字タイトル:
Safety Requirements the Prototype Fast Breeder Reactor “Monju”
第12回
高速炉機器の信頼性評価に関するガイドラインの整備
著者:
髙屋 茂,Shigeru TAKAYA,町田 秀夫,Hideo MACHIDA,神島 吉郎,Yoshio KAMISHIMA
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This paper describes the outline of the guidelines on structural reliability evaluation for the passive components of the fast breeder reactor (FBR). The guidelines are now being prepared by the working group for the system based code in the Japan society of mechanical engineers. They consist of five chapters, which are “General rules”, “Reliability evaluation”, “Failure scenario setting”, “Modeling”, and “Failure probability calculation”, respectively. In the chapter of “Reliability evaluation”, the g...
英字タイトル:
Development of Guidelines for Structural Reliability Evaluation for FBR
第12回
２次元検出器を利用した新しいＸ線応力測定法
著者:
鈴木 賢治,Kenji SUZUKI
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A method for an X-ray stress measurement can be classified into the method to determine the orientation angles for measuring the diffraction peak and the method to determine the optimum stress values. In this study, a new method for an X-ray stress measurement using an area detector is proposed and is named ”direct method”. In the direct method, the diffraction ring due to the incident X-ray beam normal to the specimen surface is used. The optimum stress values are determined by a simplex method as a k...
英字タイトル:
A New Method for X-Ray Stress Measurement Using Area Detector
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