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Journal Articles

Large-scale numerical simulation on two-phase flow behavior in a tight-lattice nuclear fuel bundle

Ose, Yasuo*; Takase, Kazuyuki; Yoshida, Hiroyuki; Kano, Takuma; Kureta, Masatoshi; Akimoto, Hajime

Dai-41-Kai Nippon Dennetsu Shimpojiumu Koen Rombunshu, 2 Pages, 2004/05

no abstracts in English

Journal Articles

Numerical analysis of two-phase flow characteristics in a reduced-moderation light water reactor

Takase, Kazuyuki; Yoshida, Hiroyuki; Ose, Yasuo*; Tamai, Hidesada; Akimoto, Hajime

Transactions of the American Nuclear Society, 89, p.88 - 89, 2003/11

no abstracts in English

Journal Articles

Development of visualization technique of analysis results on thermal-hysraulics in a fuel bundle using AVS

Takase, Kazuyuki; Masuko, Kenji*; Ose, Yasuo*; Tamai, Hidesada; Kume, Etsuo

Kashika Joho Gakkai-Shi, 23(Suppl.1), p.363 - 364, 2003/07

no abstracts in English

Journal Articles

Large-scale numerical simulations of two-phase flow behavior in a fuel bundle of a reduced-moderation light water reactor

Takase, Kazuyuki; Yoshida, Hiroyuki; Ose, Yasuo*; Tamai, Hidesada; Kano, Takuma; Akimoto, Hajime

Nippon Konsoryu Gakkai Nenkai Koenkai 2003 Koen Rombunshu, p.33 - 34, 2003/00

no abstracts in English

Journal Articles

Large-scale numerical simulations on two-phase flow behavior in a fuel bundle of RMWR with the earth simulator

Takase, Kazuyuki; Yoshida, Hiroyuki; Ose, Yasuo*; Tamai, Hidesada; Akimoto, Hajime

Proceedings of International Conference on Supercomputing in Nuclear Applications (SNA 2003) (CD-ROM), 15 Pages, 2003/00

no abstracts in English

JAEA Reports

The Study Meeting Report on the Undermoderated Spectrum Reactor; March4-5, 1998, JAERI, Tokai Japan

; Ochiai, Masaaki

JAERI-Conf 98-013, 279 Pages, 1998/09

JAERI-Conf-98-013.pdf:11.39MB

no abstracts in English

Oral presentation

Core and fuel design of BWR with multi-axial fuel shuffling

Tasaki, Yudai; Yamaji, Akifumi*; Amaya, Masaki

no journal, , 

In breeding core designs with light water, tight lattice fuel bundle design in which the coolant flow area is small is adopted to prevent the neutron moderating. Additionally, the core often consists of MOX fuel and blanket fuel, which aims to irradiate depleted uranium effectively. In preceding study, the concept of "Multi-axial fuel shuffling" has been proposed for a higher breeding core design of supercritical-water cooled reactor (SCWR), in which the core consists of multiple layers of MOX fuels and blanket fuels with independent fuel shuffling for the upper blanket layer where coolant density is lowest. As a result, the SCWR with multi-axial fuel shuffling has shown improvement of breeding performance. The same principle may be applied to BWR, since the coolant density gets low due to developing void fraction. However, the fuel rod included such a core design has two kinds of fuel pellets, and MOX fuel parts tend to get high power peaking. Therefore, it is necessary to investigate and mitigate the fuel maximum temperature and the shear stress of the boundary between MOX and blanket fuel parts which may occur by the difference of PCMI characteristics of two fuel parts. Moreover, it is possible that the cladding outer diameter change especially in MOX fuel parts may impact on the thermal-hydraulics, because the gap between rods is narrow owing to the tight lattice fuel bundle design. This study has shown the improvement of breeding performance of BWR with multi-axial fuel shuffling, and the fuel design which mitigates the above design issues. The cladding outer diameter change doesn't impact on critical heat flux ratio mostly, but depends on pressure drop of the flow channel. Therefore, this result suggests a design issue with respect to the core flow distribution.

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