Refine your search:     
Report No.
 - 
Search Results: Records 1-8 displayed on this page of 8
  • 1

Presentation/Publication Type

Initialising ...

Refine

Journal/Book Title

Initialising ...

Meeting title

Initialising ...

First Author

Initialising ...

Keyword

Initialising ...

Language

Initialising ...

Publication Year

Initialising ...

Held year of conference

Initialising ...

Save select records

Journal Articles

Research of using structural materials of decommissioning nuclear power plant for technical evaluation of ageing management for safe long term operating

Sakakibara, Yasuhide*; Yada, Hiroki

Nihon Hozen Gakkai Dai-10-Kai Gakujutsu Koenkai Yoshishu, p.477 - 481, 2013/07

Journal Articles

Functional test of the ISI system for pipes of MONJU primary heat transfer system

Maeda, Yukihiro; Yamaguchi, Toshihiko; Ueda, Masashi; Fujiki, Kazunari*

Nihon Hozen Gakkai Dai-10-Kai Gakujutsu Koenkai Yoshishu, p.599 - 601, 2013/07

An inspection system was developed for in-service inspection (ISI) of pipes in the primary heat transfer system of MONJU FBR. The system was updated and modified based on experience from the pre-service inspection and related tests. This paper describes the results of the functional tests of the new inspection system on a mockup and in MONJU, which confirmed it can satisfy the expected performance.

Oral presentation

Research of estimation method of thermal aging embrittlement on cast austenitic stainless steel

Nogiwa, Kimihiro; Onitsuka, Takashi; Abe, Teruyoshi; Sakakibara, Yasuhide; Nakamura, Takahisa

no journal, , 

Thermal embrittlement of cast austenitic stainless steel components from the decommissioned advanced thermal prototype reactor "Fugen" has been characterized. Cast stainless steel materials were obtained from recirculation pump casing. The actual time at temperature for the materials was 138,000 h at 275$$^{circ}$$C. The Fugen material show modest decrease in Charpy-impact properties and a small increase in micro-Vickers hardness in ferrite phase because of thermal aging at relatively low service temperatures. The fracture toughness prediction method (H3T model) predicts slightly lower values for Charpy-impact energy obtained from the Fugen material. The results from microstructural analysis suggest that the prediction method have the potential to provide higher accuracy by considerations of the activation energy for embrittlement at low service temperatures.

Oral presentation

Evaluation of wall thinning of the steel piping after long term operation at "Fugen" Power Station

Ando, Ryosuke; Abe, Teruyoshi; Nakamura, Takahisa

no journal, , 

Wall thinning of the steel piping of secondary cooling system after long term operation using the served materials of "Fugen" Power Station has been investigated as a series of the evaluation of the validity and availability of the utilization of serviced materials on the research projects focused on the aging. Reliability of the wall thinning rate of the steel piping has been examined referring the previous inspection data. Besides, prediction of the wall thinning rate, rationalization of the management of pipe wall thinning and verification of the countermeasures against wall thinning, have been also examined.

Oral presentation

Decontamination estimate and demonstration test results on road in the return difficult area

Tagawa, Akihiro; Yamashita, Takuya

no journal, , 

no abstracts in English

Oral presentation

Study of system safety evaluation on LTO of National project structural integrity assessment of reactor pressure vessels

Katsumata, Genshichiro; Masaki, Koichi*; Osakabe, Kazuya*; Nishikawa, Hiroyuki*; Katsuyama, Jinya; Nishiyama, Yutaka; Onizawa, Kunio

no journal, , 

To assure the structural integrity of a reactor pressure vessel (RPV) is known as one of the critical issues to maintain the safe long-term operation of a nuclear power plant. In Japan, the assessment methods for RPV integrity, stipulated in the codes and standards, have been endorsed by the regulatory body. Authors have initiated extensive research on the improvement of structural integrity assessment methods of RPVs. In this paper, we describe some research results obtained from the second-year activity. These include the study on revisiting the technical background of the methods, such as loading conditions, postulated crack definition, the other evaluation methods. In addition, studies on probabilistic methods for the applicability to the current rules and the standardization of the probabilistic analysis methods have been presented.

Oral presentation

Study on rapid wastage due to liquid droplet impingement on heat transfer tube in sg of fast breeder reactor

Kato, Keisuke*; Narabayashi, Tadashi*; Tsuji, Masashi*; Chiba, Go*; Ohshima, Hiroyuki; Kurihara, Akikazu; Uchibori, Akihiro

no journal, , 

The object of this study is to evaluate quantitatively wastage phenomena using data of tube bundle visualization test in which sodium-water reaction jet is simulated by water/steam two-phase jet. The authors remark the results of visualization test and SERAPHIM preliminary analysis.

Oral presentation

Development of heat-resistant magnetic sensor

Takaya, Shigeru; Arakawa, Hisashi*; Keyakida, Satoshi*

no journal, , 

A heat-resistant flux gate magnetic sensor has been developed. Permendur, which has high Curie point, is employed as the magnetic core material and the detection method of the external magnetic field is modified. The characteristics of the developed magnetic sensor up to 500$$^{circ}$$C were evaluated. The sensor output increased linearly with the external magnetic field in the range of $$pm$$5 G and the standard deviation at 500$$^{circ}$$C was about 0.85G.

8 (Records 1-8 displayed on this page)
  • 1