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Muramatsu, Yasuyuki; Okawara, Masami; Suzuki, Toshiyuki; Shibata, Isao; Fuketa, Toyoshi
JAEA-Technology 2007-028, 47 Pages, 2007/03
JAEA-Technology-2007-028.pdf:4.76MB
As a part of Advanced LWR Fuel Performance and Safety Research Program, irradiation experiments are conducted with high burnup uranium dioxide fuel and uranium-plutonium mixed oxide (MOX) fuel in the Nuclear Safety Research Reactor. When an irradiation capsule is transferred and loaded to the reactor core, a capsule loader is used. The previous capsule loader, however, could not have enough shielding capability against neutron flux from high burnup MOX fuel. In order to fulfill the requirement and to handle a new high pressure water capsule, accordingly, a type-B capsule loader was developed.
Murao, Hiroyuki; Muramatsu, Yasuyuki; Okawara, Masami; Shibata, Isao
JAEA-Technology 2006-062, 32 Pages, 2007/02
JAEA-Technology-2006-062.pdf:1.81MB
In NSRR (Nuclear Safety Research Reactor) experiments, test fuels are inserted in the especial capsule and the capsule will be inserted into the experimental tube which is located in the center of reactor core. In NSRR, there are 17 types of atmospheric pressure capsule, and one of them Type X-IV atmospheric pressure capsule has been produced 6 times under authorization of Ministry of Education, Culture, Sports, Science and Technology (MEXT). Application for the 7th time of authorization was submitted to the MEXT in June 2006. On this application, standard which is used to design was changed to The Japan Society of Mechanical Engineers (JSME) S NC1-2005 from the Notification 501 of the Ministry of Economy, Trade and Industry (METI). The JSME S NC1-2005 introduced the service condition in addition to the reactor condition which has been used in the Notification 501. In this application, stress limits were calculated based on the service condition. The JSME S NC1-2005 requires estimation of combined stress for Class1 support structures, which was unnecessary in the Notification 501. In this application, combined stresses were calculated and confirmed not to exceed the stress limits.
Takase, Kazuyuki; Shibata, Mitsuhiko; Ose, Yasuo*; Yoshida, Hiroyuki; Kunugi, Tomoaki*
Proceedings of 10th International Symposium on Flow Visualization (ISFV-10) (CD-ROM), 10 Pages, 2002/00
no abstracts in English
Seki, Yasushi; Kurihara, Ryoichi; Nishio, Satoshi; Ueda, Shuzo; Aoki, Isao; Ajima, Toshio*; Kunugi, Tomoaki; Takase, Kazuyuki; Shibata, Mitsuhiko
Fusion Engineering and Design, 42(1-4), p.37 - 44, 1998/09
Times Cited Count：1 Percentile：15.02(Nuclear Science & Technology)no abstracts in English
Takase, Kazuyuki; ; Kunugi, Tomoaki*
Kashika Joho Gakkai-Shi, 18(1), p.27 - 28, 1998/07
no abstracts in English
Kunugi, Tomoaki; Takase, Kazuyuki; Kurihara, Ryoichi; Seki, Yasushi;
Fusion Engineering and Design, 42, p.67 - 72, 1998/00
Times Cited Count：12 Percentile：68.65(Nuclear Science & Technology)no abstracts in English
Takase, Kazuyuki; Kunugi, Tomoaki; ; Seki, Yasushi
Fusion Engineering and Design, 42, p.83 - 88, 1998/00
Times Cited Count：13 Percentile：70.9(Nuclear Science & Technology)no abstracts in English
Kurihara, Ryoichi; Ajima, Toshio*; Kunugi, Tomoaki; Takase, Kazuyuki; Shibata, Mitsuhiko; Seki, Yasushi; *; Yamauchi, Michinori*; *; *
Fusion Engineering and Design, 42, p.61 - 66, 1998/00
Times Cited Count：7 Percentile：53.73(Nuclear Science & Technology)no abstracts in English
*; *; *; *; *; *; *; Oikawa, Toshihiro; *; *; et al.
Fusion Energy 1996, p.885 - 890, 1997/05
no abstracts in English
Kunugi, Tomoaki; Takase, Kazuyuki; Ogawa, Masuro; Shibata, Mitsuhiko
JAERI-Tech 96-012, 91 Pages, 1996/03
no abstracts in English
Takase, Kazuyuki; Kunugi, Tomoaki; Shibata, Mitsuhiko; Seki, Yasushi
Nihon Genshiryoku Gakkai-Shi, 38(11), p.904 - 906, 1996/00
Times Cited Count：0 Percentile：0.01(Nuclear Science & Technology)no abstracts in English
Terada, Atsuhiko; Shimakawa, Satoshi; Shibata, Taiju; Shiozawa, Shusaku*; Minatsuki, Isao
no journal, ,
High Temperature Gas-cooled Reactor (HTGR) has several features different from conventional light water reactors such as high passive safety characteristics, high thermal efficiency and high economy for small sized reactor with modular concept. On the other hand, one of disadvantages of HTGR with prismatic core is to require rather long-term and expensive refueling, resulting in relatively high maintenance period and cost. To solve the disadvantage, the present study challenges the core design of MHR-50 for long refueling interval by increasing core size, fuel loading and fuel burn-up. The preliminary burn-up calculation suggested that approximately 10 years of long refueling interval was found to be reasonably achieved.
