Development of a methodology to evaluate characteristics of energy technology by conjoint analysis

Hiwatari, Ryoji*; Okano, Kunihiko*; Asaoka, Yoshiyuki*; Nagano, Koji*; Ogawa, Yuichi*; Kato, Takaaki*; Tobita, Kenji; Norimatsu, Takayoshi*

Denryoku Chuo Kenkyusho Hokoku (L07012), P. 34, 2008/07

Key to take public acceptance into account on the energy system is how to evaluate and compare quantitatively the merits and the demerits of each energy system from the public viewpoint. For this purpose, a method to evaluate the property of energy technology is developed based on the conjoint analysis technique. Based on the statistical method, utility values for energy abundance, environmental load (i.e. CO emission), stability of supply, sense of security, and other features as well as economic performance, are estimated from several thousands of choice experiments to more than 1600 respondents volunteered in the study. The basic methodology developed in this study establishes the first step to assess energy technology quantitatively on a common standard, and needs further integration with other factors, such as waste generation other than CO emission.

Overview of national centralized tokamak program; Mission, design and strategy to contribute ITER and DEMO

Ninomiya, Hiromasa; Akiba, Masato; Fujii, Tsuneyuki; Fujita, Takaaki; Fujiwara, Masami*; Hamamatsu, Kiyotaka; Hayashi, Nobuhiko; Hosogane, Nobuyuki; Ikeda, Yoshitaka; Inoue, Nobuyuki; et al.

Journal of the Korean Physical Society, 49, p.S428 - S432, 2006/12

To contribute DEMO and ITER, the design to modify the present JT-60U into superconducting coil machine, named National Centralized Tokamak (NCT), is being progressed under nationwide collaborations in Japan. Mission, design and strategy of this NCT program is summarized.

Engineering design and control scenario for steady-state high-beta operation in national centralized tokamak

Tsuchiya, Katsuhiko; Akiba, Masato; Azechi, Hiroshi*; Fujii, Tsuneyuki; Fujita, Takaaki; Fujiwara, Masami*; Hamamatsu, Kiyotaka; Hashizume, Hidetoshi*; Hayashi, Nobuhiko; Horiike, Hiroshi*; et al.

Fusion Engineering and Design, 81(8-14), p.1599 - 1605, 2006/02

https://doi.org/10.1016/j.fusengdes.2005.08.066

no abstracts in English

High energy magnetic excitations from the edge-sharing CuO chains in CaYCuO

Matsuda, Masaaki; Kakurai, Kazuhisa; Yethiraj, M.*; Oka, Kunihiko*

Journal of the Physical Society of Japan, 74(5), p.1578 - 1581, 2005/05

https://doi.org/10.1143/JPSJ.74.1578

no abstracts in English

Progress in physics and technology developments for the modification of JT-60

Tamai, Hiroshi; Matsukawa, Makoto; Kurita, Genichi; Hayashi, Nobuhiko; Urata, Kazuhiro*; Miura, Yushi; Kizu, Kaname; Tsuchiya, Katsuhiko; Morioka, Atsuhiko; Kudo, Yusuke; et al.

Plasma Science and Technology, 6(1), p.2141 - 2150, 2004/02

https://doi.org/10.1088/1009-0630/6/1/006

The dominant issue for the the modification program of JT-60 (JT-60SC) is to demonstrate the steady state reactor relevant plasma operation. Physics design on plasma parameters, operation scenarios, and the plasma control method are investigated for the achievement of high-. Engineering design and the R&D on the superconducting magnet coils, radiation shield, and vacuum vessel are performed. Recent progress in such physics and technology developments is presented.

Annual Report on Activities of Radiation Protection Division at JNC Tokai Works in Fiscal Year of 2002

Shinohara, Kunihiko; Asano, Tomohiro; Momose, Takumaro; Takeishi, Minoru; Kobayashi, Hirohide; Oka, Tsutomu; Takasaki, Koji

JNC TN8440 2003-020, 125 Pages, 2003/09

JNC-TN8440-2003-020.pdf:11.14MB

This annual report summarizes the activities of the Radiation Protection Division at JNC Tokai Works in fiscal 2002.The Tokai Works undertakes various research and development for the reprocessing of spent fuel, plutonium fuel fabrication, fast reactor fuel recycling technology, and radioactive waste treatment and disposal, all of which are done under strict safety management.The major radiation facilities in the Tokai Works are the Tokai Reprocessing Plant (TRP), which has been in operation since 1977, three MOX fuel fabrication facilities, the first of which has been in operation since 1965, the Chemical Processing Facility (CPF) where fast reactor (FR) reprocessing technologies are being developed, and various other radioisotope and uranium research laboratories.The Radiation Protection Division is responsible for radiation control in and around these facilities, including personnel monitoring, workplace monitoring, consultation on radiological work planning and evaluation, monitoring of gas and liquid waste effluents, environmental monitoring, instrumentation, calibration, quality assurance, and safety research. The Division also provides technical support and cooperation to other international and domestic institutes in the radiation protection field.In fiscal 2002, the results of radiological monitoring showed the situation to be normal, and no radiological incident or accident occurred. The maximum annual effective dose to radiation workers was 6.5 mSv and the mean annual effective dose was 0.1 mSv. Individual doses were kept within the annual dose limit specified in the safety regulations. The estimated effective dose caused by gas and liquid effluents from the TRP to members of the public around the Tokai Works was 4.2 * 10mSv. Environmental monitoring and effluent control were performed appropriately in compliance with safety regulation and standards.

Objectives and design of the JT-60 superconducting tokamak

Ishida, Shinichi; Abe, Katsunori*; Ando, Akira*; Cho, T.*; Fujii, Tsuneyuki; Fujita, Takaaki; Goto, Seiichi*; Hanada, Kazuaki*; Hatayama, Akiyoshi*; Hino, Tomoaki*; et al.

Nuclear Fusion, 43(7), p.606 - 613, 2003/07

https://doi.org/10.1088/0029-5515/43/7/314

no abstracts in English

Detailed magnetic structure of the coupled edge-sharing CuO chains in CaYCuO

Matsuda, Masaaki; Kakurai, Kazuhisa; Yamaguchi, Hirotaka*; Ito, Toshimitsu*; Lee, C.-H.*; Oka, Kunihiko*

Applied Physics A, 74(Suppl.1), p.S637 - S639, 2002/12

https://doi.org/10.1007/s003390201569

no abstracts in English

Conceptual design of solid breeder blanket system cooled by supercritical water

Enoeda, Mikio; Ohara, Yoshihiro; Akiba, Masato; Sato, Satoshi; Hatano, Toshihisa; Kosaku, Yasuo; Kuroda, Toshimasa*; Kikuchi, Shigeto*; Yanagi, Yoshihiko*; Konishi, Satoshi; et al.

JAERI-Tech 2001-078, 120 Pages, 2001/12

JAERI-Tech-2001-078.pdf:8.3MB

This report is a summary of the design works, which was discussed in the design workshop held in 2000 for the demonstration (DEMO) blanket aimed to strengthen the commercial competitiveness and technical feasibility simultaneously. The DEMO blanket must supply the feasibility and experience of the total design of the power plant and the materials. This conceptual design study was performed to determine the updated strategy and goal of the R&D of the DEMO blanket which applies the supercritical water cooling proposed in A-SSTR, taking into account the recent progress of the plasma research and reactor engineering technology.

Possible scenario to start up DT fusion plant without initial loading of tritium

Konishi, Satoshi; Asaoka, Yoshiyuki*; Hiwatari, Ryoji*; Okano, Kunihiko*

Purazuma, Kaku Yugo Gakkai-Shi, 76(12), p.1309 - 1312, 2000/12

http://ci.nii.ac.jp/naid/110003825454

no abstracts in English