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JAEA Reports

Data survey and compilation of material property tables of irradiated stainless steel for evaluation of radiation effects on structural material properties of core internals in pressurized water reactors (Contract research)

Kasahara, Shigeki; Fukuya, Koji*; Fujimoto, Koji*; Fujii, Katsuhiko*; Chimi, Yasuhiro

JAEA-Review 2018-013, 171 Pages, 2019/01

JAEA-Review-2018-013.pdf:6.89MB

For structural integrity assessment of reactor internals of light water reactors, it is important to evaluate and predict the property changes of structural materials, based on existing data obtained from austenitic stainless steel irradiated with neutrons. Compilation of the data into tables is valuable for discussing the representative or the most probable values of the properties applied to the assessment. When the data compilation, the data must be distinguished clearly in consideration of different service conditions of core internals of pressurized water reactors (PWR) and boiling water reactors. Main objective of this work is to provide material property tables of irradiated austenitic stainless steel which will be applicable for assessment of structural integrity of core internals of PWRs. To compile the table, published literature reporting irradiated stainless steel data were surveyed and screened by considering the service conditions of PWRs. In addition to the data, various parameters for the data evaluation, e.g. chemical compositions and pre-treatments of the materials, irradiation and examination conditions, were extracted from the literature, and listed into tables.

JAEA Reports

Data survey and compilation of material property tables of irradiated stainless steel for evaluation of radiation effects on structural material properties of core internals in boiling water reactors (Contract research)

Kasahara, Shigeki; Fukuya, Koji*; Koshiishi, Masato*; Fujii, Katsuhiko*; Chimi, Yasuhiro

JAEA-Review 2018-012, 180 Pages, 2018/11

JAEA-Review-2018-012.pdf:10.71MB

For structural integrity assessment of reactor internals of light water reactors, it is important to evaluate and predict the property changes of structural materials, based on existing data obtained from austenitic stainless steel irradiated with neutrons. Compilation of the data into tables is valuable for discussing the representative or the most probable values of the properties applied to the assessment. In the process of the data compilation, the data must be distinguished clearly in consideration of different service conditions of core internals of boiling water reactors (BWR) and pressurized water reactors. Main objective of this work is to provide material property tables of irradiated austenitic stainless steel which will be applicable for assessment of structural integrity of core internals of BWRs. To compile the table, published literature reporting irradiated stainless steel data were surveyed and screened by considering the service conditions of BWRs. In addition to the data, various parameters for the data evaluation, e.g. chemical compositions and pre-treatments of the materials, irradiation and examination conditions, were extracted from the literature, and listed into the tables.

Journal Articles

Efficient isotope ratio analysis of uranium particles in swipe samples by total-reflection X-ray fluorescence spectrometry and secondary ion mass spectrometry

Esaka, Fumitaka; Watanabe, Kazuo; Fukuyama, Hiroyasu; Onodera, Takashi; Esaka, Konomi; Magara, Masaaki; Sakurai, Satoshi; Usuda, Shigekazu

Journal of Nuclear Science and Technology, 41(11), p.1027 - 1032, 2004/11

 Times Cited Count:60 Percentile:95.55(Nuclear Science & Technology)

A new particle recovery method and a sensitive screening method were developed for subsequent isotope ratio analysis of uranium particles in safeguards swipe samples. The particles in the swipe sample were recovered onto a carrier by means of vacuum suction 8211; impact collection method. When grease coating was applied to the carrier, the recovery efficiency was improved to 48 %, which is superior to that of conventionally-used ultrasoneration method. Prior to isotope ratio analysis with secondary ion mass spectrometry (SIMS), total reflection X-ray fluorescence spectrometry (TXRF) was applied to screen the sample for the presence of uranium particles. By the use of Si carriers in TXRF analysis, the detection limit of 22 pg was achieved for uranium. By combining these methods with SIMS, the isotope ratios of $$^{235}$$U/$$^{238}$$U for individual uranium particles were efficiently determined.

Journal Articles

Vibronic mechanism of high-${it Tc}$ superconductivity

Tachiki, Masashi*; Machida, Masahiko; Egami, Takeshi*

Physical Review B, 67(17), p.174506_1 - 174506_12, 2003/05

 Times Cited Count:47 Percentile:85.19(Materials Science, Multidisciplinary)

no abstracts in English

Journal Articles

Radiation measurement for safeguards environmental samples by imaging plate

Yasuda, Kenichiro; Sakurai, Satoshi; Gunji, Hideho; Usuda, Shigekazu

Journal of Nuclear Science and Technology, 39(Suppl.3), p.552 - 555, 2002/11

In order to contribute to the strengthened safeguards system based on the Program 93+2 of the IAEA, Japan Atomic Energy Research Institute (JAERI) constructed the CLEAR facility (Clean Laboratory for Environmental Analysis and Research) and is developing analytical technology for ultra trace amounts of nuclear materials in environmental samples. To avoid cross-contamination among the samples and contamination of the clean rooms, radioactive materials in the samples to be introduced into the CLEAR facility will be limited to a certain amount. For this purpose the authors have examined the feasibility of Imaging-plate method, which is a kind of autoradiography and is suitable for determination on distribution of low-level radioactivity in the samples. Preliminary examination with $$beta$$-ray (K-40), the linearity was obtained in the range of 0.01 - 0.2 Bq. The experiments with $$alpha$$-ray (Sm-147) suggested the detection limit of 0.01 Bq, which was equivalent to 2 $$mu$$g of natural uranium. At the presentation, the results on actual environmental samples will be reported.

Journal Articles

Development of trace analytical technology for nuclear materials in the clean laboratory for environmental analysis and research

Usuda, Shigekazu; Watanabe, Kazuo; Sakurai, Satoshi; Magara, Masaaki; Hanzawa, Yukiko; Esaka, Fumitaka; Miyamoto, Yutaka; Yasuda, Kenichiro; Saito, Yoko; Gunji, Katsubumi*; et al.

KEK Proceedings 2001-14, p.88 - 92, 2001/06

no abstracts in English

Journal Articles

Current status of JAERI program on development of ultra-trace-analytical technology for safeguards environmental samples

Adachi, Takeo; Usuda, Shigekazu; Watanabe, Kazuo; Sakurai, Satoshi; Magara, Masaaki; Hanzawa, Yukiko; Esaka, Fumitaka; Yasuda, Kenichiro; Saito, Yoko; Takahashi, Masato; et al.

IAEA-SM-367/10/02 (CD-ROM), 8 Pages, 2001/00

no abstracts in English

Journal Articles

Development of environmental sample analysis techniques for safeguards and its current status

Magara, Masaaki; Hanzawa, Yukiko; Esaka, Fumitaka; Miyamoto, Yutaka; Yasuda, Kenichiro; Tsuruta, Yasuhiro; Tsuda, Shinji; Watanabe, Kazuo; Usuda, Shigekazu; Nishimura, Hideo; et al.

Kaku Busshitsu Kanri Gakkai Nihon Shibu Dai-20-Kai Kinen Taikai Rombunshu, p.183 - 187, 1999/11

no abstracts in English

JAEA Reports

None

Ikeda, Takao*; Yoshida, Hideji*

PNC TJ1281 98-001, 376 Pages, 1998/02

PNC-TJ1281-98-001.pdf:14.57MB

None

JAEA Reports

Source term modeling and analysis for Vault/Trench facilities located in an unsaturated zone

Munakata, Masahiro; Kimura, Hideo; Matsuzuru, Hideo

JAERI-Research 95-046, 57 Pages, 1995/06

JAERI-Research-95-046.pdf:2.37MB

no abstracts in English

JAEA Reports

Electron beam irradiation experiments of a divertor module at KFA

; Akiba, Masato; Araki, Masanori; J.Linke*; R.Duwe*; E.Wallura*

JAERI-M 93-048, 22 Pages, 1993/03

JAERI-M-93-048.pdf:1.43MB

no abstracts in English

Oral presentation

Studies on the peptide drug discovery of cancer using radioisotope

Sasaki, Ichiro; Hanaoka, Hirofumi*; Yamada, Keiichi*; Watanabe, Shigeki; Sugo, Yumi; Ohshima, Yasuhiro; Ishioka, Noriko

no journal, , 

no abstracts in English

Oral presentation

Studies on a new selection method of peptides with affinity to cancer using RI-labeled random peptide libraries

Sasaki, Ichiro; Hanaoka, Hirofumi*; Yamada, Keiichi*; Watanabe, Shigeki; Sugo, Yumi; Ohshima, Yasuhiro; Ishioka, Noriko

no journal, , 

no abstracts in English

Oral presentation

Applicability study of laser beam butt welding for pipe structure maintenance with ultrasonic guided wave

Furusawa, Akinori; Nishimura, Akihiko; Torimoto, Kazuhiro; Takenaka, Yusuke*; Toyama, Ryoji*; Nakamoto, Hiroyuki*

no journal, , 

The aim of this work presented here is to investigate the applicability of ultrasonic guided wave for evaluation of laser beam butt welding quality. First, laser beam butt welded pipes are prepared. Two pipes are jointed and continuous wave laser beam is irradiated on the line. The test pipes are divided into two groups according to the difference in laser welding quality. One group is fine quality welded, another group is poor. Second, ultrasonic guided wave testing experiment is performed on the pipes. Torsional mode guided wave is excited by Electromagnetic Acoustic Transducers. Finally, the experimental results are analyzed and issues are discussed. The reflection wave bullet from the poor welded line is clearly observed, whereas no reflection from fine welded line. It is found that the ultrasonic guided wave technologies have the potential for laser beam butt welding line evaluation.

Oral presentation

Research and development on preceding processing methods for contaminated water management waste at Fukushima Daiichi Nuclear Power Station, 8; Investigation of method for screening test of contaminated water management waste applied to solidification by cement and Alkali Activated Material

Taniguchi, Takumi; Namiki, Masahiro*; Osugi, Takeshi; Sone, Tomoyuki; Kuroki, Ryoichiro; Kikuchi, Michio*; Yamamoto, Takeshi*; Otsuka, Taku*; Kaneda, Yoshihisa*; Osawa, Norihisa*; et al.

no journal, , 

no abstracts in English

Oral presentation

Oral presentation

Research and development on preceding processing methods for contaminated water management waste at Fukushima Daiichi Nuclear Power Station, 32; Investigation of downsizing method by using centrifuge tube for screening of solidifiable contaminated water management waste

Tabata, Koichi; Namiki, Masahiro*; Osawa, Norihisa*; Sakamoto, Ryo*; Kaneda, Yoshihisa*; Kakuda, Ayaka; Sone, Tomoyuki; Osugi, Takeshi; Kuroki, Ryoichiro

no journal, , 

no abstracts in English

Oral presentation

Development of probabilistic risk assessment method considering multi-hazards, 1; Research plan and aim

Takada, Tsuyoshi; Nishida, Akemi; Choi, B.; Takito, Kiyotaka; Tsutsumi, Hideaki*; Muramatsu, Ken; Kubo, Kotaro*

no journal, , 

no abstracts in English

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