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Dai-3-Kai Kantaiheiyo Genshiryoku Kaigi, 0 Pages, 2002/12
FBR technology makes it possible to use uranium resources effetively by adopting flexibly a variety of fuel types such as plutonium and minor actinides. This technology can also contribute to the reduction of the reducion of the environmental burden bytransmutation oflong-lived radioactive materials in high-levelradioactive waste. From these points of view, it is desired to develop FBR technology worldwide. Considering the prwsent situation in which the development of FBR technology has shown a tendency to decline worldwide, we would like to propose the use of MONJU as a worldwide joint property.
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Dai-13-Kai Kantaiheiyo Genshiryoku Kaigi No Paneru Keiji, 0 Pages, 2002/10
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Oigawa, Hiroyuki; Sasa, Toshinobu; Takano, Hideki; Tsujimoto, Kazufumi; Nishihara, Kenji; Kikuchi, Kenji; Kurata, Yuji; Saito, Shigeru; Futakawa, Masatoshi; Umeno, Makoto*; et al.
Proceedings of 13th Pacific Basin Nuclear Conference (PBNC 2002) (CD-ROM), 8 Pages, 2002/10
To reduce the burden on the final disposal of the nuclear waste, the Acclelerator-Driven System (ADS) which can transmute minor actinides efficiently has been studied in JAERI. The proposed ADS design is an 800MWth subcritical core with lead-bismuth coolant and minor-actinide nitride fuel driven by a neutron source of a superconductivity linear accelerator with 30MW and a lead-bismuth spallation target. To realize the ADS, many research and development are under way in the fields of the accelerator, the spallation target and the nitride fuel. Moreover, a new experimental facility, the Transmutation Experimental Facility, is proposed under a framework of the High-Intensity Proton Accelerator Project to study the feasibility of the ADS from physics and engineering aspects.
Iwamura, Takamichi; Okubo, Tsutomu; Kureta, Masatoshi; Nakatsuka, Toru; Takeda, Renzo*; Yamamoto, Kazuhiko*
Proceedings of 13th Pacific Basin Nuclear Conference (PBNC 2002) (CD-ROM), 7 Pages, 2002/10
In order to ensure sustainable energy supply in Japan, the reduced-moderation water reactor (RMWR) has been developed by JAERI since 1998. MOX fuel assemblies with tight lattice arrangement are used to increase the conversion ratio. In order to establish negative void reactivity coefficient, the core should be short and flat to increase neutron leakage from the core. The core designs were accomplished to a large core with 1,356MWe and a small core with 330MWe. For both cores, negative void coefficient and natural circulation cooling of the core were realized. To confirm thermal-hydraulic feasibility, critical heat flux experiments were performed using 7-rod bundles with the gap width of 1mm and 1.3mm. The results indicated that enough cooling was assured for the tight lattice core. Further R&D studies, including large scale thermal-hydraulic experiments, reactor physics experiments, development of high burn-up fuel cladding material and simplified reprocessing technology, are necessary to realize commercial introduction of RMWR by 2020's for the replacement of current generation LWRs.
; Kitabata, Takuya; ; Takagi, Hisatsugu; ;
Dai-13-Kai Kantaiheiyo Genshiryoku Kaigi 2002, 0 Pages, 2002/00
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Iijima, Takashi; ;
Dai-13-Kai Kantaiheiyo Genshiryoku Kaigi 2002, 0 Pages, 2002/00
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; Ieda, Yoshiaki; Konomura, Mamoru; Shimakawa, Yoshio
Kantaiheiyo Genshiryoku Kaigi, 0 Pages, 2002/00
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