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Journal Articles

Preparedness and response for nuclear or radiological emergency as a designated public corporation

Okuno, Hiroshi; Okamoto, Akiko; Ebine, Noriya; Hayakawa, Tsuyoshi; Tanaka, Tadao

Proceedings of 27th International Conference on Nuclear Engineering (ICONE-27) (Internet), 15 Pages, 2019/05

In the event of a nuclear or radiological emergency, the Japan Atomic Energy Agency (JAEA) as a designated public corporation assigned in the Disaster Countermeasures Basic Act of Japan undertakes a role to support the national government and local governments. This paper (1) illuminates the roles of the JAEA as a designated public corporation for preparedness and response to a nuclear or radiological emergency of nuclear facilities; (2) summarizes emergency response activities of the JAEA in accordance with its Disaster Management Operation Plan against the off-site radiological emergencies attributed to a loss of control of the Tokyo Electric Power Company (TEPCO)'s Fukushima Daiichi Nuclear Power Station that occurred in 2011; and (3) reports its activities in normal times especially participation in the drills organized by the national government and local governments in the light of the Basic Disaster Management Plan of Japan and Local Disaster Management Plans of prefectural governments, respectively.

Journal Articles

${it In situ}$ magnetic measurements under neutron radiation in Fe metal and low carbon steel

Takahashi, Seiki*; Kikuchi, Hiroaki*; Ara, Katsuyuki*; Ebine, Noriya; Kamada, Yasuhiro*; Kobayashi, Satoru*; Suzuki, Masahide

Journal of Applied Physics, 100(2), p.023902_1 - 023902_6, 2006/07

 Times Cited Count:32 Percentile:25.23(Physics, Applied)

Magnetic minor hysteresis loops of low carbon steel and Fe metal have been measured during neutron radiation at 563 K in a nuclear reactor. For investigation of nucleation mechanism of copper precipitates and dislocation loops, special attention was paid to minor-loop coefficients, which are deduced from simple relations between minor-loop parameters and are very sensitive to lattice defects. We found that with increasing neutron fluence, the minor-loop coefficients of low carbon steel sharply increase and show a maximum at the fluence of 1$$times$$10$$^{19}$$ cm$$^{-2}$$, followed by a slow decrease. The appearance of the maximum suggests the presence of two mechanisms of internal stress; while copper precipitates and dislocation loops in the matrix make the internal stress increase, those grown in the vicinity of dislocations compensate the internal stress of dislocations. On the other hand, the minor-loop coefficients show a monotonic increase with neutron fluence in Fe metal.

JAEA Reports

Report of Examination of the Sample from Core Shroud (2F2-H3) at Fukushima Dai-ni Power Station Unit-2 (Contract research)

The Working Team for Examination of the Sample from Core Shrouds and Primary Loop Recirculation Pipi; Nakajima, Hajime*; Shibata, Katsuyuki; Tsukada, Takashi; Suzuki, Masahide; Kiuchi, Kiyoshi; Kaji, Yoshiyuki; Kikuchi, Masahiko; Ueno, Fumiyoshi; Nakano, Junichi; et al.

JAERI-Tech 2004-015, 114 Pages, 2004/03

JAERI-Tech-2004-015.pdf:38.06MB

The Tokyo Electric Power Company (TEPCO) visually inspected the weld joint of core shroud at Fukushima Dai-ni Nuclear Power Station Unit-2 by a direction of the Nuclear and Industrial Agency, cracks were observed at outer side of the ring weld joint (H3) between a core shroud middle trunk and a middle ring. TEPCO has conducted a material examination with Nippon Nuclear Fuel Development Co. Ltd. (NFD) on the specimen including cracks sampled from the core shroud. The present examination has been performed with the objective to independently investigate and evaluate the materials by jointly attending the examination with NFD from the planning stage. Based on results of the present examination, the probable presence of tensile residual stress by welding process and dissolved oxygen contents in the cooling water, it was shown that the cracks were considered to be stress corrosion cracking (SCC). However, the cause of the cracks needs more consideration on the way of shroud construction.

Journal Articles

Aging degradation of light water reactor materials; Reactor internal and pressure vessel materials

Tsukada, Takashi; Ebine, Noriya

Nippon AEM Gakkai-Shi, 9(2), p.171 - 177, 2001/06

no abstracts in English

Journal Articles

Evaluation of the magnetic and mechanical properties of reactor pressure vessel steels by incremental permeability change curve measurements

Ebine, Noriya; Suzuki, Masahide

Nippon Oyo Jiki Gakkai-Shi, 25(4-2), p.1051 - 1054, 2001/04

no abstracts in English

Journal Articles

Evaluation of nuclear reactor pressure vessel integrity by magnetic interrogation and problems of relevant magnetic field analysis

Ara, Katsuyuki*; Ebine, Noriya

Denki Gakkai Magunetikkusu Kenkyukai Shiryo (MAG-01-55), p.1 - 6, 2001/03

no abstracts in English

Journal Articles

Nondestructive magnetic measurements to evaluate material degradation of nuclear reactor structure; The Present state of research activities

Ara, Katsuyuki*; Ebine, Noriya

Denki Gakkai Magunetikkusu Kenkyukai Shiryo (MAG-00-182), p.23 - 31, 2000/09

no abstracts in English

Journal Articles

Evaluation of magnetic and mechanical properties of reactor pressure vessel steels by incremental permeability change curve measurements

Ebine, Noriya; Suzuki, Masahide; Ara, Katsuyuki*

Denki Gakkai Magunetikkusu Kenkyukai Shiryo (MAG-00-195), p.45 - 48, 2000/09

no abstracts in English

Oral presentation

An Examination of correlation between IASCC susceptibility and electromagnetic properties, 1

Nemoto, Yoshiyuki; Uchimoto, Tetsuya*; Keyakida, Satoshi*; Nagae, Yuji; Takaya, Shigeru; Ebine, Noriya; Tsukada, Takashi

no journal, , 

It was suggested by the authors that electromagnetic method could detect irradiation assisted stress corrosion cracking (IASCC) of austenitic stainless steel in advance of crack initiation. Authors investigated the mechanism using mock specimens of radiation induced segregation (RIS). SCC susceptibility and electromagnetic properties of the mock specimens were studied. Results were compared with the data of irradiated specimens and mechanism of electromagnetic diagnosis were discussed. A sensor system will be developed by application of these mechanism.

Oral presentation

An Examination of correlation between IASCC susceptibility and electromagnetic properties, 2

Nemoto, Yoshiyuki; Takaya, Shigeru; Ebine, Noriya; Tsukada, Takashi; Uchimoto, Tetsuya*; Keyakida, Satoshi*

no journal, , 

no abstracts in English

Oral presentation

A Study of testing method for non distractive monitoring of IASCC susceptibility

Nemoto, Yoshiyuki; Miwa, Yukio; Takaya, Shigeru; Ebine, Noriya; Tsukada, Takashi; Uchimoto, Tetsuya*; Keyakida, Satoshi*

no journal, , 

Authors reported previously that magnetic parameter seems to depend on irradiation assisted stress corrosion cracking susceptibility of high purity model austenitic stainless steels. This study aimed to investigate mechanism of the dependence. Electron diffraction patterns obtained by transmission electron microscopy were evaluated to study precipitation in irradiated specimens. Influence of element segregation on electro magnetic property of austenitic stainless steel was investigated applying mockup specimens. It was shown that magnetic phases were formed in irradiated austenitic stainless steels. Mockup experiments showed that radiation induced segregation can bring magnetic phase formation along grain boundaries. The magnetic phase was thought to involve with mechanism of magnetic parameter dependence on irradiation assisted stress corrosion cracking susceptibility.

Oral presentation

A Study of testing method for non distractive monitoring of IASCC susceptibility

Nemoto, Yoshiyuki; Miwa, Yukio; Takaya, Shigeru; Ebine, Noriya; Tsukada, Takashi; Uchimoto, Tetsuya*; Keyakida, Satoshi*

no journal, , 

Authors reported previously that magnetic parameter seems to depend on irradiation assisted stress corrosion cracking susceptibility of high purity model austenitic stainless steels. This study aimed to investigate mechanism of the dependence. Electron diffraction patterns obtained by transmission electron microscopy were evaluated to study precipitation in irradiated specimens. Influence of element segregation on electro magnetic property of austenitic stainless steel was investigated applying mockup specimens. It was shown that magnetic phases were formed in irradiated austenitic stainless steels. Mockup experiments showed that radiation induced segregation can bring magnetic phase formation along grain boundaries. The magnetic phase was thought to involve with mechanism of magnetic parameter dependence on irradiation assisted stress corrosion cracking susceptibility.

Oral presentation

Studies on plant aging of light water reactors using the Fugen NPS

Ebine, Noriya

no journal, , 

In order to provide the technical information for the safety regulation on the aging management technical evaluation for the current commercial light water reactors (LWRs), wall thinning of the steel piping and verification of the countermeasures against SCC using the served materials of "Fugen" Power Station retired after 25 years operation have been investigated. Reliability of the wall thinning rate of the steel piping was examined referring the inspection data and the predicted calculations. Using these results, wall thinning data base was established. The validity of the management of pipe wall thinning at Fugen was examined. For SCC, there was no observed crack by metallurgical structure observations and ultrasonic inspections. It was thought that SCC was controlled judging also from the measurements of residual stress and the analysis of heat affected zone. The effectiveness of SCC management techniques at Fugen was examined.

Oral presentation

Fragility evaluation of wall-thinned pipes using PASCAL-EC

Ebine, Noriya; Yamaguchi, Yoshihito; Katsuyama, Jinya; Nishida, Akemi; Li, Y.

no journal, , 

A probabilistic analysis code PASCAL-EC (PFM Analysis of Structural Components in Aging LWR - Erosion and Corrosion) have been improved for evaluating structural integrity of wall thinned pipes on the basis of the Monte Carlo method. In order to perform the fragility evaluation for wall-thinned pipes, several functions are introduced to PASCAL-EC in this work, such as probabilistic evaluation model to consider the uncertainty of seismic response stress, a simple evaluation model to considered the increase of the seismic stress due to wall thinning and failure evaluation methods for wall-thinned pipes. This paper provides some details of these models and preliminary results of fragility evaluation using improved PASCAL-EC code for wall-thinned pipes in nuclear power plants.

Oral presentation

Patent

オーステナイトステンレス鋼の中性子照射による照射誘起応力腐食割れの予兆診断方法

高屋 茂; 根本 義之; 海老根 典也

欅田 理*

JP, 2008-301850  Patent licensing information  Patent publication (In Japanese)

【課題】原子炉、粒子加速器等の構造材料において発生する照射誘起応力腐食割れ(IASCC)のき裂発生以前の予兆を評価するシステムを提供すること。 【解決手段】交流磁化法により、被検体の第3高調波電圧値を測定し、予め求められている第3高調波電圧値の変化の大きさとIASCC感受性の度合いとの相関関係を示すデータベースを参照して、被検体のIASCC感受性の度合いを求める。さらに、前記被検体の渦電流法プローブ電圧を測定し、予め求められている渦電流法プローブ電圧値の変化とIASCC感受性の度合いとの相関関係を示すデータベースを参照して、前記被検体のIASCC感受性の度合いを求め、求められたIASCC感受性の度合いが、前記第3高調波電圧値の変化から求められたIASCC感受性の度合いから所定の誤差範囲にあるかどうかを求める。

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