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Journal Articles

$$Q_{beta}$$ measurements of $$^{158,159}$$Pm, $$^{159,161}$$Sm, $$^{160-165}$$Eu, $$^{163}$$Gd and $$^{166}$$Tb using a total absorption BGO detector

Hayashi, Hiroaki*; Akita, Yukinori*; Suematsu, Osamu*; Shibata, Michihiro*; Asai, Masato; Sato, Tetsuya; Ichikawa, Shinichi; Nishinaka, Ichiro; Nagame, Yuichiro; Osa, Akihiko; et al.

European Physical Journal A, 34(4), p.363 - 370, 2007/12

 Times Cited Count:17 Percentile:71.95(Physics, Nuclear)

$$Q_{beta}$$ values of $$^{160-165}$$Eu and $$^{163}$$Gd were measured for the first time using a total absorption BGO detector, and the data of $$^{158,159}$$Pm, $$^{159,161}$$Sm, and $$^{166}$$Tb obtained previously were reanalyzed. These nuclei were produced by the proton-induced fission of $$^{238}$$U at the JAEA-Tokai tandem accelerator facility, and separated from the reaction products using an on-line isotope separator. The deduced mass excesses and two-neutron separation energies were compared with those of atomic mass evaluations and theoretical predictions.

Journal Articles

Glovebox Dismantling Activities and Decommissioning Plan for Plutonium Fuel Fabricating Facility

Kitamura, Akihiro; Okada, Takashi; Asazuma, Shinichiro; Uematsu, Shinichi; Ishibashi, Takashi

Proceedings of 12th International Conference on Nuclear Engineering (ICONE-12) (CD-ROM), 6 Pages, 2004/00

The gloveboxes and process equipment used at plutonium fuel handling facilities had to bereplaced due to deterioration or change of object.

Journal Articles

Development of Foam Floating Decontamination System for Radioactive Solid Wastes from MOX-Fuel Fabrication

Okada, Takashi; Uematsu, Shinichi; Tobita, Noriyuki; Kato, Junya

9th International Conference on Environmental Remediation and Radioactive Waste Management (ICEM '03), 0 Pages, 2003/00

None

Journal Articles

DECOMMISSIONING OF A PLUTONIUM-CONTAMINATED WASTE INCINERATOR FACILITY

Uematsu, Shinichi; Tobita, Noriyuki; Koakutsu, Toru

Proceedings of 8th International Conference on Radioactive Waste Management and Environmental Remediation (ICEM '01) (CD-ROM), 0 Pages, 2002/00

None

Journal Articles

Dismantling of Gloveboxes for MOX Fuel Production by A Glovebox Dismantling Facility

Uematsu, Shinichi; Tobita, Noriyuki; Kashiro, Kashio

WM'02, 0 Pages, 2002/00

None

Journal Articles

Irradiation Experiment of MOX Fuel Assembly for Advanced Thermal Reactor

Uematsu, Shinichi; Mitsugi, Takeshi; ; Kobayashi, Tetsuro*; Yokoya, Jun*

Nihon Genshiryoku Gakkai-Shi, 39(10), p.870 - 880, 1997/10

 Times Cited Count:1 Percentile:14.24(Nuclear Science & Technology)

None

JAEA Reports

None

Onuki, Norihiko; ; Shuji, Yoshiyuki; Uematsu, Shinichi; ; ;

PNC TN8410 97-272, 143 Pages, 1997/08

PNC-TN8410-97-272.pdf:5.33MB

None

Journal Articles

Development of high burn-up MOX fuel for ATR

Uematsu, Shinichi; ; Onuki, Norihiko; ;

ANS Topical Meeting on LWR Fuel Perfomance, 0 Pages, 1997/00

None

Journal Articles

Neutronics analysis of a duples-type Mox-Gd fuel in ATR

Yamaguchi, Takashi; Shuji, Yoshiyuki; Uematsu, Shinichi

Proceedings of ANS Topical Meeting on Advances in Nuclear Fuel Management II, 0 Pages, 1997/00

None

Journal Articles

Core performance of the heavy water reactor ATR as a Pu burmer

Uematsu, Shinichi; Yamaguchi, Takashi; ; Matsumoto, Mitsuo

Proceedings of International Conference on Future Nuclear Systems (GLOBAL'97), 0 Pages, 1997/00

None

Journal Articles

The design method for the ATR high burn-up MOX fuel

; Uematsu, Shinichi

Specialists 'Meeting on Nuclear Fuel and Control Rods, 0 Pages, 1996/10

The Power Reactor and Nuclear Fuel Development Corporation(PNC)hasdeveloped the advanced thermal reactor(ATR). PNC is demonstrating MOX fuel utilization in a prototype of ATR, Fugen(165MWe), in which 638 MOX fuel assemblies have been loaded without a failure since 1979. PNC is developing the high burn-up MOX fuel for the ATR to contribute to MOX fuels for thermal reactors. The statistical design evalu

Journal Articles

None

Onuki, Norihiko; ; ; Uematsu, Shinichi

Donen Giho, (96), p.18 - 28, 1995/12

None

Journal Articles

Evaluation of pie on MOX fuels for demonstration ATR

Uematsu, Shinichi; Kikuchi, Keiichi

Proceedings of 1994 International Topical Meeting on Light Water Reactor Fuel Performance, 0 Pages, 1994/00

None

Journal Articles

Evaluation of pie on MOX fuels for demonstration ATR

Uematsu, Shinichi; ; Mitsugi, Takeshi

Proceedings of ANS International Topical Meeting on Light Water Reactor Fuel Performance, 0 Pages, 1994/00

None

Journal Articles

None

Uematsu, Shinichi; ; ; Abe, Tomiyuki; Matsumoto, Mitsuo

Donen Giho, (87), p.53 - 61, 1993/09

None

Journal Articles

Recent Results of PIE on MOX Fuel for Demonstration ATR

Uematsu, Shinichi; ; ; Matsumoto, Mitsuo

ANP 92 INTERNATIONAL CONFTY OF ADVANCED NUCLEAR P, 2, 19-1 Pages, 1992/00

None

Journal Articles

None

Numata, Koji; Uematsu, Shinichi

Gekkan "Eko Indasutori", , 

None

17 (Records 1-17 displayed on this page)
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