Refine your search:     
Report No.
 - 
Search Results: Records 1-20 displayed on this page of 25

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

Internally Cu-stabilized RHQT Nb$$_{3}$$Al superconductors with Ta matrix

Takeuchi, Takao*; Tagawa, Kohei*; Noda, Tetsuji*; Banno, Nobuya*; Iijima, Yasuo*; Kikuchi, Akihiro*; Kitaguchi, Hitoshi*; Kosuge, Michio*; Tsuchiya, Kiyosumi*; Koizumi, Norikiyo; et al.

IEEE Transactions on Applied Superconductivity, 16(2), p.1257 - 1260, 2006/06

 Times Cited Count:6 Percentile:38.07(Engineering, Electrical & Electronic)

Next generation nuclear fusion magnets would require a high-current conductor in fields more than 16 T. A CIC conductor of the rapid RHQT processed Nb$$_{3}$$Al may be a promising candidate. Good deformability of intermediately-formed bcc supersaturated-solid solution indeed allowed fabricating such a CIC conductor, which would be subsequently transformation annealed. Ag has been internally included as a basic constituent of a round strand so far, because Ag is almost non-reactive with Nb matrix during the RHQ. However, both of Ag and Nb are not suitable nuclei from the viewpoint of radioactivity when irradiated with neutrons. Recently, we have succeeded in replacing the Nb matrix with Ta that has the advantage of shorter half-life of radioactivity. In the present study, an attempt has been made to replace the Ag internal stabilizer with Cu, in the aim of further reducing radioactivity, based on anticipation that Ta would be less reactive with Cu than Nb did.

Journal Articles

Development of re-irradiation techniques using JMTR

Matsui, Yoshinori; Ide, Hiroshi; Itabashi, Yukio; Kikuchi, Taiji; Ishikawa, Kazuyoshi; Abe, Shinichi; Inoue, Shuichi; Shimizu, Michio; Iwamatsu, Shigemi; Watanabe, Naoki*; et al.

UTNL-R-0416, p.5_1 - 5_10, 2002/03

no abstracts in English

Journal Articles

Post-irradiation annealing and re-irradiation technique for LWR reactor pressure vessel material

Matsui, Yoshinori; Ide, Hiroshi; Itabashi, Yukio; Kikuchi, Taiji; Ishikawa, Kazuyoshi; Abe, Shinichi; Inoue, Shuichi; Shimizu, Michio; Iwamatsu, Shigemi; Watanabe, Naoki*; et al.

KAERI/GP-195/2002, p.33 - 40, 2002/00

Studies on the irradiation damage of the material of the RPV are inevitable for the LWR. Recently, the researches of annealing effect on the irradiation damage of RPV material were extensively carried out using specimens irradiated in the JMTR of the JAERI. As the next step, an annealing test of irradiated specimens and re-irradiation of annealed specimens were planned. The aim of the test is to evaluate the effect of annealing by comparing the damage of irradiated specimen, its recovery by annealing and the damage after re-irradiation. For the re-irradiation test of this study, JAERI developed a new capsule in which the specimens can be exchanged before and after annealing, and, re-irradiated afterward. The development of the capsule consisted of the design and fabrication of airtight connector for thermocouples and mechanical seal device which was fit to remote handling. Remote operation procedures for handling the radioactive capsule and for exchanging specimens were carefully performed. The results of the re-irradiation proved that the development was technically successful.

Journal Articles

A Mechanical design for ferritic steels to reduce toroidal field ripple in the JFT-2M

Nakayama, Takeshi*; Yamamoto, Masahiro; Abe, Mitsushi*; Shibata, Takatoshi; Otsuka, Michio*; Akiyama, Takashi*; Sato, K.*; Kikuchi, Kazuo; Wada, Y.*; Koike, Tsuneyuki; et al.

Proceedings of the 18th IEEE/NPSS Symposium on Fusion Engineering (SOFE '99), p.227 - 230, 1999/10

no abstracts in English

JAEA Reports

The First loading fuel elements and power-up for JRR-2

JRR-2 Control Office; Kambara, Toyozo; Shoda, Katsuhiko; Hirata, Yutaka; Shoji, Tsutomu; Kohayakawa, Toru; Morozumi, Minoru; Kambayashi, Yuichiro; Shitomi, Hajimu; Kokanezawa, Takashi; et al.

JAERI 1027, 57 Pages, 1962/09

JAERI-1027.pdf:4.76MB

no abstracts in English

JAEA Reports

Efficiency testing of the control and cooling systems of JRR-2

Kambara, Toyozo; Shoda, Katsuhiko; Hirata, Yutaka; Shoji, Tsutomu; Haginoya, Kinichi; Kohayakawa, Toru; Yamaki, Jikei; Yokota, Mitsuo; Horiki, Oichiro; Yuhara, Shunichi; et al.

JAERI 1023, 120 Pages, 1962/09

JAERI-1023.pdf:8.67MB

no abstracts in English

JAEA Reports

Treatment and analysis of the water and gas in JRR-2

JRR-2 Operations Office; Kambara, Toyozo; Shoda, Katsuhiko; Hirata, Yutaka; Shoji, Tsutomu; Haginoya, Kinichi; Kohayakawa, Toru; Yamaki, Jikei; Yokota, Mitsuo; Horiki, Oichiro; et al.

JAERI 1024, 79 Pages, 1962/08

JAERI-1024.pdf:5.66MB

no abstracts in English

JAEA Reports

Critical experiments and characteristic measurement for JRR-2

JRR-2 Critical Experiments Group; Kambara, Toyozo; Shoda, Katsuhiko; Hirata, Yutaka; Shoji, Tsutomu; Kohayakawa, Toru; Morozumi, Minoru; Kambayashi, Yuichiro; Shitomi, Hajimu; Kokanezawa, Takashi; et al.

JAERI 1025, 62 Pages, 1962/03

JAERI-1025.pdf:4.6MB

no abstracts in English

Oral presentation

Research and development on preceding processing methods for contaminated water management waste at Fukushima Daiichi Nuclear Power Station, 5; Gamma-ray irradiation test on solidified body of cement and Alkali Activated Material

Taniguchi, Takumi; Imaizumi, Ken*; Namiki, Masahiro*; Osugi, Takeshi; Kuroki, Ryoichiro; Kikuchi, Michio*; Yamamoto, Takeshi*; Kaneda, Yoshihisa*; Haga, Kazuko*

no journal, , 

It is important to understand fundamental solidification characteristics of contaminated water management waste at Fukushima Daiichi Nuclear Power Station. The Solidified bodies are fabricated with cementitious material and Alkali Activated Material, and are irradiated with Gamma-ray.

Oral presentation

Research and development on preceding processing methods for contaminated water management waste at Fukushima Daiichi Nuclear Power Station, 4; Evaluation of dissolution behavior on solidified body of cement and Alkali Activated Material

Kaneda, Yoshihisa*; Haga, Kazuko*; Shibata, Masahito*; Kuranaga, Mebae*; Kikuchi, Michio*; Yamamoto, Takeshi*; Kato, Jun; Osugi, Takeshi; Kuroki, Ryoichiro

no journal, , 

Solidified cement and alkali activated materials was made, and used for dissolution test to obtain basic data of solidification on the waste caused by the contaminated water treatment at Fukushima Daiichi Nuclear Power Station.

Oral presentation

Research and development on preceding processing methods for contaminated water management waste at Fukushima Daiichi Nuclear Power Station, 3; Outline of characteristics evaluation study on solidified body of cement and Alkali Activated Material

Kikuchi, Michio*; Yamamoto, Takeshi*; Otsuka, Taku*; Kawato, Takaya*; Kaneda, Yoshihisa*; Shibata, Masahito*; Haga, Kazuko*; Taniguchi, Takumi; Osugi, Takeshi; Kuroki, Ryoichiro

no journal, , 

Summary of the study which is for characterization of Solidified cement and alkali activated materials was carried out due to obtain the data available for applicability evaluation low-temperature solidification on the waste caused by the contaminated water treatment at Fukushima Daiichi Nuclear Power Station.

Oral presentation

Research and development on preceding processing methods for contaminated water management waste at Fukushima Daiichi Nuclear Power Station, 2; Investigation of approach for selecting solidification techniques applied to contaminated water management waste

Furukawa, Shizue*; Koyama, Tadafumi*; Kikuchi, Michio*; Otsuka, Taku*; Yamamoto, Takeshi*; Imaizumi, Ken*; Osugi, Takeshi; Nakazawa, Osamu; Kuroki, Ryoichiro

no journal, , 

In order to evaluate the application to the solidification of the water treatment secondary waste generated from Fukushima Daiichi Nuclear Power Station, research concerning the approach of applicability evaluation was conducted for solidification technology of practical scale.

Oral presentation

Research and development on preceding processing methods for contaminated water management waste at Fukushima Daiichi Nuclear Power Station, 13; Gamma-ray irradiation characteristics of solidified materials containing carbonate slurry

Kato, Jun; Imaizumi, Ken*; Osugi, Takeshi; Sone, Tomoyuki; Kuroki, Ryoichiro; Kikuchi, Michio*; Yamamoto, Takeshi*; Otsuka, Taku*; Kaneda, Yoshihisa*; Osawa, Norihisa*

no journal, , 

Solidified cement and Alkali Activated Materials (AAM) containing simulated carbonated slurry was prepared, and the amount of Hydrogen gas generation on gamma-ray irradiation was determined. The obtained data was compared with the data of solidified material without any content of waste, and the effect for Hydrogen gas generation with the material containing simulated carbonated slurry was evaluated.

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

Research and development on preceding processing methods for contaminated water management waste at Fukushima Daiichi Nuclear Power Station, 9; Synthesis of simulated carbonate slurry

Nakashio, Nobuyuki*; Kawasoe, Takahiro*; Aikawa, Kohei*; Kikuchi, Michio*; Yamamoto, Takeshi*; Kaneda, Yoshihisa*; Haga, Kazuko*; Osugi, Takeshi; Sone, Tomoyuki; Kuroki, Ryoichiro

no journal, , 

Simulated carbonate slurry was synthesized to obtain basic data for the low temperature processing of the waste generated from contaminated water treatment at Fukushima Daiichi Nuclear Power Station. An overview of the study and some of the results obtained are reported here.

Oral presentation

Research and development on preceding processing methods for contaminated water management waste at Fukushima Daiichi Nuclear Power Station, 10; Characteristic evaluation of carbonate slurry-containing solidified body formed by cement or alkali activated material

Kikuchi, Michio*; Yamamoto, Takeshi*; Otsuka, Taku*; Kawato, Takaya*; Kaneda, Yoshihisa*; Shibata, Masahito*; Haga, Kazuko*; Osugi, Takeshi; Sone, Tomoyuki; Kuroki, Ryoichiro

no journal, , 

In order to obtain data to be used in the evaluation of the applicability of low temperature processing to carbonate slurry generated by contaminated water treatment at Fukushima Daiichi Nuclear Power Station, the basic properties of the solidified cement and alkali activated material blended simulated carbonated slurry were evaluated. An overview of the study and some of the results obtained are reported here.

Oral presentation

Research and development on preceding processing methods for contaminated water management waste at Fukushima Daiichi Nuclear Power Station, 11; Dissolution test of solidified body of cement and Alkali Activated Material

Kaneda, Yoshihisa*; Haga, Kazuko*; Shibata, Masahito*; Osawa, Norihisa*; Kikuchi, Michio*; Yamamoto, Takeshi*; Kawato, Takaya*; Osugi, Takeshi; Sone, Tomoyuki; Kuroki, Ryoichiro

no journal, , 

Solidified cement and alkali activated material blending carbonated slurry were prepared and their dissolution tests were carried out in order to obtain basic data for the low temperature processing of the waste generated by contaminated water treatment at Fukushima Daiichi Nuclear Power Station. An overview of the study and some of the results obtained are reported here.

Oral presentation

Research and development on preceding processing methods for contaminated water management waste at Fukushima Daiichi Nuclear Power Station, 15-2; Investigation of approach for selecting solidification techniques applied to contaminated water management waste

Kikuchi, Michio*; Furukawa, Shizue*; Koyama, Tadafumi*; Otsuka, Taku*; Yamamoto, Takeshi*; Imaizumi, Ken*; Osugi, Takeshi; Sone, Tomoyuki; Kuroki, Ryoichiro

no journal, , 

no abstracts in English

Oral presentation

Research and development on preceding processing methods for contaminated water management waste at Fukushima Daiichi Nuclear Power Station, 19; $$gamma$$-ray irradiation characteristics of solidified materials containing iron slurry

Sato, Junya; Kakuda, Ayaka; Imaizumi, Ken*; Kikuchi, Michio*; Yamamoto, Takeshi*; Kaneda, Yoshihisa*; Osawa, Norihisa*; Osugi, Takeshi; Sone, Tomoyuki; Kuroki, Ryoichiro

no journal, , 

no abstracts in English

Oral presentation

Research and development on preceding processing methods for contaminated water management waste at Fukushima Daiichi Nuclear Power Station, 16; Consideration of quantification of method for screening test of contaminated water management waste applied to solidification by cement and Alkali Activated Material

Kakuda, Ayaka; Taniguchi, Takumi; Namiki, Masahiro*; Kikuchi, Michio*; Yamamoto, Takeshi*; Kaneda, Yoshihisa*; Osawa, Norihisa*; Osugi, Takeshi; Sone, Tomoyuki; Kuroki, Ryoichiro

no journal, , 

no abstracts in English

25 (Records 1-20 displayed on this page)