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Journal Articles

Consequence analysis of a postulated nuclear excursion in BWR spent fuel pool using 1/$$f^{beta}$$ spectrum model of randomization

Simanullang, I.; Yamane, Yuichi; Kikuchi, Takeo; Tonoike, Kotaro

Annals of Nuclear Energy, 147, p.107675_1 - 107675_6, 2020/11

 Times Cited Count:1 Percentile:39.17(Nuclear Science & Technology)

JAEA Reports

Analysis of post irradiation examination of used BWR fuel with SWAT4.0

Kikuchi, Takeo; Tada, Kenichi; Sakino, Takao; Suyama, Kenya

JAEA-Research 2017-021, 56 Pages, 2018/03

JAEA-Research-2017-021.pdf:2.15MB

The criticality management of the fuel debris is one of the most important research issues in Japan. The current criticality management adopts the fresh fuel assumption. The adoption of the fresh fuel assumption for the criticality control of the fuel debris is difficult because the k$$_{rm eff}$$ of the fuel debris could exceed 1.0 in most of cases which the fuel debris contains water and does not contain neutron absorbers such as gadolinium. Therefore, the adoption of the burnup credit is considered. The prediction accuracy of the isotopic composition of used nuclear fuel must be required to adopt the burnup credit for the treatment of the fuel debris. JAEA developed a burnup calculation code SWAT4.0 to obtain reference calculation results of the isotopic composition of the used nuclear fuel. This code is used to evaluate the composition of fuel debris. In order to investigate the prediction accuracy of SWAT4.0, we analyzed the PIE of BWR obtained from 2F2DN23.

Journal Articles

Analysis of used BWR fuel assay data with the integrated burnup code system SWAT4.0

Tada, Kenichi; Kikuchi, Takeo*; Sakino, Takao; Suyama, Kenya

Journal of Nuclear Science and Technology, 55(2), p.138 - 150, 2018/02

 Times Cited Count:2 Percentile:33.17(Nuclear Science & Technology)

The criticality safety of the fuel debris in Fukushima Daiichi Nuclear Power Plant is one of the most important issues and the adoption of the burnup credit is desired for the criticality analysis. The assay data of used nuclear fuel irradiated in 2F2 is evaluated to validate SWAT4.0 for BWR fuel burnup problem. The calculation results revealed that number density of many heavy nuclides and FPs showed good agreement with the experimental data except for $$^{235}$$U, $$^{237}$$Np, $$^{238}$$Pu and Sm isotopes. The cause of the difference is assumption of the initial number density and void ratio and overestimation of the capture cross section of $$^{237}$$Np. The C/E-1 values do not depend on the types of fuel rods (UO$$_{2}$$ or UO$$_{2}$$-Gd$$_{2}$$O$$_{3}$$) and it is similar to that for the PWR fuel. These results indicate that SWAT4.0 appropriately analyzes the isotopic composition of the BWR fuel and it has sufficient accuracy to be adopted in the burnup credit evaluation of the fuel debris.

Journal Articles

Development of small specimen test techniques for the IFMIF test cell

Wakai, Eiichi; Kim, B. J.; Nozawa, Takashi; Kikuchi, Takayuki; Hirano, Michiko*; Kimura, Akihiko*; Kasada, Ryuta*; Yokomine, Takehiko*; Yoshida, Takahide*; Nogami, Shuhei*; et al.

Proceedings of 24th IAEA Fusion Energy Conference (FEC 2012) (CD-ROM), 6 Pages, 2013/03

Journal Articles

Introduction to plasma fusion energy

Takamura, Shuichi*; Kado, Shinichiro*; Fujii, Takashi*; Fujiyama, Hiroshi*; Takabe, Hideaki*; Adachi, Kazuo*; Morimiya, Osamu*; Fujimori, Naoji*; Watanabe, Takayuki*; Hayashi, Yasuaki*; et al.

Kara Zukai, Purazuma Enerugi No Subete, P. 164, 2007/03

no abstracts in English

Journal Articles

High performance tokamak experiments with a ferritic steel wall on JFT-2M

Tsuzuki, Kazuhiro; Kimura, Haruyuki; Kawashima, Hisato; Sato, Masayasu; Kamiya, Kensaku; Shinohara, Koji; Ogawa, Hiroaki; Hoshino, Katsumichi; Bakhtiari, M.; Kasai, Satoshi; et al.

Nuclear Fusion, 43(10), p.1288 - 1293, 2003/10

 Times Cited Count:39 Percentile:76.12(Physics, Fluids & Plasmas)

no abstracts in English

Journal Articles

Swelling behavior of F82H steel irradiated by triple/dual ion beams

Wakai, Eiichi; Kikuchi, Kenji; Yamamoto, Shunya; Aruga, Takeo; Ando, Masami; Tanigawa, Hiroyasu; Taguchi, Tomitsugu; Sawai, Tomotsugu; Oka, Keiichiro*; Onuki, Somei*

Journal of Nuclear Materials, 318, p.267 - 273, 2003/05

 Times Cited Count:58 Percentile:96(Materials Science, Multidisciplinary)

no abstracts in English

Journal Articles

Effects of triple ion beams in ferritic/martensitic steel on swelling behavior

Wakai, Eiichi; Sawai, Tomotsugu; Furuya, Kazuyuki; Naito, Akira; Aruga, Takeo; Kikuchi, Kenji; Yamashita, Shinichiro*; Onuki, Somei*; Yamamoto, Shunya; Naramoto, Hiroshi; et al.

Journal of Nuclear Materials, 307-311(Part.1), p.278 - 282, 2002/12

 Times Cited Count:46 Percentile:93.45(Materials Science, Multidisciplinary)

no abstracts in English

JAEA Reports

Development of eddy current techniques at PIE facility; phase II testing for FCCI measurement

Kikuchi, Shin; Kitazawa, Takeo; ; Matsumoto, Shinichiro

JNC TN9410 2001-003, 84 Pages, 2000/07

JNC-TN9410-2001-003.pdf:2.12MB

Eddy current techniques have been tested for future Post irradiated Experiment ;PIE applications outside hot cell(the following, cell outside). As the result, applicability to the defects inspection such as the cladding tube material was able to be confirmed, and an outlook to the application to the irradiation material was obtained. The last time, report described results of the external surface defects, inside defects, and open holes outside hot cell except for Fuel-Cladding Chemical Interaction (FCCI) measurement testing This paper mainly describes the results of the trial FCCI measurement testing outside hot cell. Other tests include the results of external surface defects, inside defects, and open holes in the proofreading tests. The proofreading tests used a standard defect pin inside hot cell. In the trial FCCI measurement testing outside hot cell, the correlation between reduction in thickness and eddy current signal value was comfirmed, and the prospect of FCCI measurement by the eddy current testing was examined. As the result, the optimum conditions for measuring the FCCI quantity are respectively (1)carrier speed of the pin :20mm/sec, (2) test frequency : 32kHz, (3)phase : ODEG, (4) gain :-10dB, (5)filter : 0. The correlation between trial FCCI quantity and eddy current signal value was found on the basis of the test result, and the prospect which could detect FCCI was obtained when there is reduction in thickness of over 50 $$mu$$m for the cladding tube with wall thickness quantity of the 300 $$mu$$m order. And, the proofreading test inside hot cell on eddy current measurements were confirmed to be equivalent to the performance test outside hot cell.

Journal Articles

Non-dimensional transport scaling and its correlation with local transport properties in JT-60U plasmas

Shirai, Hiroshi; Takizuka, Tomonori; Kikuchi, Mitsuru; Mori, Masahiro; Nishitani, Takeo; Ishida, Shinichi; Kamada, Yutaka; Sato, Masayasu; Isei, Nobuaki; Koide, Yoshihiko; et al.

IAEA-CN-60/A2-17, 0, p.355 - 364, 1995/00

no abstracts in English

Journal Articles

Ripple induced fast ion loss and related effects in JT-60U

Tobita, Kenji; Tani, Keiji; Kusama, Yoshinori; Nishitani, Takeo; Ikeda, Yoshitaka; Neyatani, Yuzuru; S.V.Konovalov*; Kikuchi, Mitsuru; Koide, Yoshihiko; Hamamatsu, Kiyotaka; et al.

Nuclear Fusion, 35(12), p.1585 - 1591, 1995/00

 Times Cited Count:63 Percentile:88(Physics, Fluids & Plasmas)

no abstracts in English

Journal Articles

Internal transport barrier on q=3 surface and poloidal plasma spin up in JT-60U high-$$beta$$$$_{p}$$ discharges

Koide, Yoshihiko; Kikuchi, Mitsuru; Mori, Masahiro; Tsuji, Shunji; Ishida, Shinichi; Asakura, Nobuyuki; Kamada, Yutaka; Nishitani, Takeo; Kawano, Yasunori; Hatae, Takaki; et al.

Physical Review Letters, 72(23), p.3662 - 3665, 1994/06

 Times Cited Count:250 Percentile:98.52(Physics, Multidisciplinary)

no abstracts in English

Journal Articles

Attainment of high fusion reactivity under high bootstrap current fraction in JT-60U

Nishitani, Takeo; Ishida, Shinichi; Kikuchi, Mitsuru; Azumi, Masafumi; Yamagiwa, Mitsuru; Fujita, Takaaki; Kamada, Yutaka; Kawano, Yasunori; Koide, Yoshihiko; Hatae, Takaki; et al.

Nuclear Fusion, 34(8), p.1069 - 1079, 1994/00

 Times Cited Count:28 Percentile:69.36(Physics, Fluids & Plasmas)

no abstracts in English

Journal Articles

Enhanced confinement of high bootstrap current discharges in JT-60U

Ishida, Shinichi; Matsuoka, Mamoru; Kikuchi, Mitsuru; Tsuji, Shunji; Nishitani, Takeo; Koide, Yoshihiko; Ozeki, Takahisa; Fujita, Takaaki; Nakamura, Hiroo; Hosogane, Nobuyuki; et al.

Plasma Physics and Controlled Nuclear Fusion Research 1992, Vol.1, p.219 - 233, 1993/00

no abstracts in English

Journal Articles

Investigation of particle transport in JT-60 using a perturbation method

Nagashima, Keisuke; Fukuda, Takeshi; Kikuchi, Mitsuru; Hirayama, Toshio; Nishitani, Takeo; Takeuchi, Hiroshi

Nuclear Fusion, 30(11), p.2367 - 2375, 1990/11

 Times Cited Count:7 Percentile:33.28(Physics, Fluids & Plasmas)

no abstracts in English

Journal Articles

JT-60 upgrade program

Kikuchi, Mitsuru; Ando, Toshiro; Araki, Masanori; ; Horiike, Hiroshi; Ikeda, Yoshitaka; ; Koizumi, Koichi; Matsukawa, Makoto; ; et al.

Fusion Technology 1988, p.287 - 292, 1989/00

no abstracts in English

Journal Articles

JT-60U system design

Matsukawa, Makoto; Ando, Toshiro; Araki, Masanori; ; Horiike, Hiroshi; Ikeda, Yoshitaka; Kikuchi, Mitsuru; ; Koizumi, Koichi; ; et al.

Fusion Technology 1988, p.293 - 297, 1989/00

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

Progress of engineering design in IFMIF-EVEDA project

Wakai, Eiichi; Kikuchi, Takayuki; Hirano, Michiko; Ida, Mizuho; Niitsuma, Shigeto; Kimura, Haruyuki; Nishitani, Takeo; Yamamoto, Michiyoshi; Matsumoto, Hiroshi; Sugimoto, Masayoshi; et al.

no journal, , 

no abstracts in English

Oral presentation

Research facilities completed in Rokkasho for BA activities

Ohira, Shigeru; Kikuchi, Takayuki; Oshima, Takayuki; Kasuya, Kenichi*; Yonemoto, Kazuhiro*; Sugimoto, Masayoshi; Nishitani, Takeo; Okumura, Yoshikazu

no journal, , 

For Broader Approach Activities, which are joint project between Japan and Europe, JAEA who is the Japanese implementing Agency, has established "International Fusion Energy Research Centre (IFERC)" in Rokkasho, Aomori Japan. At research facilities in IFERC, DEMO R&D Building and CSC&REC Building, in which research and development activities are carried out, experimental equipment and components had been installed and in operation until the end of 2011. The outline of those facilities are described in a poster.

24 (Records 1-20 displayed on this page)