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JAEA Reports

Development of type-B capsule loader in the NSRR (Contract research)

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.

JAEA Reports

Design of type X-IV atmospheric pressure capsule for irradiation test based on JSME S NC-1 2005

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.

JAEA Reports

Development of sodium facilities for NSRR fast reactor fuel tests, 1; Purification, charging and test loops

Nakamura, Takehiko; Ikeda, Yoshikazu; Yachi, Shigeyasu; Ogawara, Masami; Yoshinaga, Makio; Takariko, Isao; Toyokawa, Shunji; Katanishi, Shoji; Sobajima, Makoto

JAERI-Tech 2000-019, p.162 - 0, 2000/03

JAERI-Tech-2000-019.pdf:6.02MB

no abstracts in English

Journal Articles

Experimental study of differences in single-phase forced-convection heat transfer characteristics between upflow and downflow for narrow rectangular channel

Sudo, Yukio; *; ; ; Kaminaga, Masanori

Journal of Nuclear Science and Technology, 22(3), p.202 - 212, 1985/00

 Times Cited Count:33 Percentile:94.49(Nuclear Science & Technology)

no abstracts in English

Journal Articles

Experimental study of differences in DNB heat flux between upflow and downflow in a vertical channel

Sudo, Yukio; *; ; Kaminaga, Masanori;

Journal of Nuclear Science and Technology, 22(8), p.604 - 618, 1985/00

 Times Cited Count:59 Percentile:97.81(Nuclear Science & Technology)

no abstracts in English

Oral presentation

High burnup PWR fuel behavior under RIA conditions, 1; Cladding deformation and fission gas release during power transient

Sugiyama, Tomoyuki; Tomiyasu, Kunihiko; Sasajima, Hideo; Umeda, Miki; Nagase, Fumihisa; Fuketa, Toyoshi; Okawara, Masami; Honda, Junichi

no journal, , 

no abstracts in English

Oral presentation

Behavior of high burnup fuels under Reactivity-Initiated Accident (RIA) and Loss-of-Coolant Accident (LOCA) conditions, 1; An Outline of the program

Fuketa, Toyoshi; Nagase, Fumihisa; Sugiyama, Tomoyuki; Nishino, Yasuharu; Okawara, Masami

no journal, , 

no abstracts in English

Oral presentation

Preliminary review of NSRR aseismic safety evaluation with revision of safety guideline

Awa, Yasuaki; Murao, Hiroyuki; Okawara, Masami; Wada, Shigeru

no journal, , 

no abstracts in English

Oral presentation

Integrity investigation of the pool-lining of the NSRR with ultrasonic device, 2; Investigation result

Kawashima, Kazuhito; Taguchi, Yuji; Muramatsu, Yasuyuki; Suzuki, Toshiyuki; Okawara, Masami

no journal, , 

no abstracts in English

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