Initialising ...
Initialising ...
Initialising ...
Initialising ...
Initialising ...
Initialising ...
Initialising ...
Sudo, Katsuo; Takano, Tatsuo; Takeuchi, Kentaro; Kihara, Yoshiyuki; Kato, Masato
Proceedings of International Conference on Toward and Over the Fukushima Daiichi Accident (GLOBAL 2011) (CD-ROM), 5 Pages, 2011/12
Japan Atomic Energy Agency has been contracted to advance the Fast Reactor Cycle Technology Development project. As one part of the project, a simplified MOX pellet fabrication method has been developed for fast reactor fuels. In previous reports, feasibility of a simplified MOX pellet fabrication method was confirmed through hot and cold laboratory-scale experiments. The die wall lubrication pressing technology was one of the important technologies included in the development of the simplified MOX pellet fabrication method. In the work described here, a pressing machine with a die wall lubrication system was developed, and MOX pellet fabrication experiments were carried out on the kilogram MOX scale.
Takano, Tatsuo; Sudo, Katsuo; Takeuchi, Kentaro; Kihara, Yoshiyuki; Kato, Masato
Proceedings of International Conference on Toward and Over the Fukushima Daiichi Accident (GLOBAL 2011) (CD-ROM), 7 Pages, 2011/12
Development of high burn-up fuels is essential to improve economy of the fast reactor fuel cycle. Increase of fuel burn-up is known to cause fuel-cladding chemical interaction (FCCI) and it mainly determines a lifetime of fuel pin. In order to extend a lifetime of fuel pin by mitigating FCCI, development of low oxygen-to-metal (O/M) MOX fuel has been carried out in plutonium fuel development center of JAEA. MOX fuel needs adjustment of the O/M ratio to less than 1.97 for high burn-up of 150 GWd/t. Therefore, O/M adjustment technology is one of the main subjects in development of a simplified MOX pellet fabrication method which has been advanced in the FaCT (Fast reactor Cycle Technology development) project. In previous work, changes in O/M ratio of MOX pellet during heat treatment were calculated from measurement results of oxygen potentials. On the basis of above calculation, heating tests were carried out to prepare low O/M ratio MOX pellets on a laboratory scale. The O/M ratios obtained in the heating tests were well consistent with calculation results. In the present study, a kilogram MOX scale furnace to adjust O/M ratio of MOX pellets for targeted value has been developed as next step.
Mizuno, Mineo; Haga, Tetsuya; Sudo, Katsuo; Takeuchi, Kentaro; Okita, Takatoshi; Kihara, Yoshiyuki
JAEA-Technology 2011-009, 100 Pages, 2011/06
JAEA-Technology-2011-009.pdf:32.59MB
Crystalline cellulose granulated to sizes from 70 to 100 micron was previously used as pore former (PF) to fabricate low density MOX pellets for MONJU. When sale of Avicel was discontinued, it became necessary to find a substitute PF. Then, small scale fabrication tests of MOX pellets with candidate PFs were conducted. Three candidate PFs, cellulose beads, CEOLUS and CELPHERE, were examined in the tests. The results are summarized below. (1) The CELPHERE gave MOX pellets with almost same density depression performance as pellets using Avicel, and standards deviation of the sintered densities of pellets was the smallest. (2) MOX pellets with CELPHERE had lower incidence of observable defects. (3) MOX pellets with CELPHERE had almost the same O/M as pellets with Avicel. (4) MOX pellets with CELPHERE had lower incidence of micro cracks. (5) The densification amount of pellets with CELPHERE was almost the same as that of pellets with Avicel. It was concluded CELPHERE was a suitable substitute for Avicel.
Higuchi, Hidekazu; Osugi, Takeshi; Nakashio, Nobuyuki; Momma, Toshiyuki; Tohei, Toshio; Ishikawa, Joji; Iseda, Hirokatsu; Mitsuda, Motoyuki; Ishihara, Keisuke; Sudo, Tomoyuki; et al.
JAEA-Technology 2007-038, 189 Pages, 2007/07
JAEA-Technology-2007-038-01.pdf:15.13MBJAEA-Technology-2007-038-02.pdf:38.95MBJAEA-Technology-2007-038-03.pdf:48.42MBJAEA-Technology-2007-038-04.pdf:20.53MBJAEA-Technology-2007-038-05.pdf:10.44MB
The Advanced Volume Reduction Facilities (AVRF) is constructed to manufacture the waste packages of radioactive waste for disposal in the Nuclear Science Research Institute of the Japan Atomic Energy Agency. The AVRF is constituted from two facilities. The one is the Waste Size Reduction and Storage Facility (WSRSF) which is for reducing waste size, sorting into each material and storing the waste package. The other is the Waste Volume Reduction Facility (WVRF) which is for manufacturing the waste package by volume reducing treatment and stabilizing treatment. WVRF has an induction melting furnace, a plasma melting furnace, an incinerator, and a super compactor for treatment. In this report, we summarized about the basic concept of constructing AVRF, the constitution of facilities, the specifications of machineries and the state of trial operation until March of 2006.
Inagaki, Shigeru*; Takenaga, Hidenobu; Ida, Katsumi*; Isayama, Akihiko; Tamura, Naoki*; Takizuka, Tomonori; Shimozuma, Takashi*; Kamada, Yutaka; Kubo, Shin*; Miura, Yukitoshi; et al.
Nuclear Fusion, 46(1), p.133 - 141, 2006/01
Times Cited Count：54 Percentile：85.24(Physics, Fluids & Plasmas)no abstracts in English
Inagaki, Shigeru*; Takenaga, Hidenobu; Ida, Katsumi*; Isayama, Akihiko; Tamura, Naoki*; Takizuka, Tomonori; Shimozuma, Takashi*; Kamada, Yutaka; Kubo, Shin*; Miura, Yukitoshi; et al.
Proceedings of 20th IAEA Fusion Energy Conference (FEC 2004) (CD-ROM), 8 Pages, 2004/11
no abstracts in English
Hatakeyama, Yuichi; Sudo, Kenji; Kanazawa, Hiroyuki
JAERI-Tech 2004-033, 29 Pages, 2004/03
JAERI-Tech-2004-033.pdf:1.65MB
The amount of fission gas (Kr, Xe) in irradiated fuel pellet increases with extending the burn up and that exerts a serious influence upon thermal and mechanical properties of light water reactor fuel. Therefore, the accumulation of the data on the release behavior of fission gas is important in the investigation program of safety and reliability for extended burn up fuel. In the post irradiation examination at the Reactor Fuel Examination Facility in JAERI,the fission gas which released into the plenum region from UO
pellet during irradiation has been measured by puncturing test of irradiated fuel rod. The results of puncturing test show the most of fission gas remained in the pellet. It can be seen that the additional release of fission gas might occur under higher burn up and accident conditions. To know the fission gas release behavior from irradiated fuel, the Out Gas analyzer(OGA)which has the performance to heat up the UO pellet stepwise up to 2300
C and to measure the released fission gas instantly from the pellet has been developed and installed at RFEF.
Moribayashi, Kengo; Sudo, Keiko*; Zhidkov, A. G.; Sasaki, Akira; Kagawa, Takashi*
Laser and Particle Beams, 19(4), p.643 - 646, 2001/10
Times Cited Count：6 Percentile：30.53(Physics, Applied)no abstracts in English
Shirasu, Noriko; Yamashita, Toshiyuki; Kanazawa, Hiroyuki; Kimura, Yasuhiko; Sudo, Kenji; Magara, Masaaki; Inagawa, Jun; Kono, Nobuaki; Nakahara, Yoshinori
JAERI-Research 2001-018, 23 Pages, 2001/03
JAERI-Research-2001-018.pdf:1.48MB
no abstracts in English
Moribayashi, Kengo; Zhidkov, A. J.*; Sasaki, Akira; Sudo, Keiko; Suzuki, Shingo*
Atomic Collision Research in Japan, No.27, p.1 - 3, 2001/00
no abstracts in English
Moribayashi, Kengo; Zhidkov, A. G.; Sasaki, Akira; Sudo, Keiko; Suzuki, Shingo*
Proceedings of 2nd International Conference on Inertial Fusion Sciences and Applications (IFSA 2001), p.1182 - 1185, 2001/00
no abstracts in English
Moribayashi, Kengo; Sasaki, Akira; Zhidkov, A. G.; Ueshima, Yutaka; Sudo, Keiko*; Kagawa, Takashi*
Atomic Collision Research in Japan, No. 26, p.111 - 113, 2000/00
no abstracts in English
*; Sudo, Ken*; Suzuki, Kenichiro*; Hata, Koji*; Ouchi, H.*; *
JNC TJ7400 99-008, 225 Pages, 1999/02
no abstracts in English
Tsukada, Takashi; Shiba, Kiyoyuki; G.E.C.Bell*; Nakajima, Hajime; Kizaki, Minoru; Omi, Masao; Sudo, Kenji; Goto, Ichiro
JAERI-M 92-081, 27 Pages, 1992/06
no abstracts in English
Shimo, Michito*; Horita, Masakuni*; Sudo, Ken*; Hibiya, Keisuke*; Yasuno, Masamitsu*
PNC TJ1449 92-007, 255 Pages, 1992/02
None
Horita, M.*; Furuichi, Mitsuaki*; Ito, K.*; Sudo, Ken*
PNC TJ7449 91-001VOL2, 406 Pages, 1991/05
PNC-TJ7449-91-001VOL2.pdf:11.33MB
no abstracts in English
Horita, M.*; Furuichi, Mitsuaki*; Ito, K.*; Sudo, Ken*
PNC TJ7449 91-001VOL1, 406 Pages, 1991/05
PNC-TJ7449-91-001VOL1.pdf:3.51MB
no abstracts in English
Saito, Shinzo; Tanaka, Toshiyuki; Sudo, Yukio; Baba, Osamu; ; Hishida, Makoto; ; ; Shinohara, Yoshikuni; *; et al.
Nihon Genshiryoku Gakkai-Shi, 32(9), p.847 - 871, 1990/09
no abstracts in English
Hoshiya, Taiji; ; Kizaki, Minoru; *; Sudo, Kenji; ;
JAERI-M 89-205, 68 Pages, 1989/12
no abstracts in English
