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Journal Articles

Compatibility of FBR materials with sodium

Furukawa, Tomohiro; Kato, Shoichi; Yoshida, Eiichi

Journal of Nuclear Materials, 392(2), p.249 - 254, 2009/07

 Times Cited Count:41 Percentile:92.45(Materials Science, Multidisciplinary)

In order to incorporate an evaluation procedure for sodium environmental effects of core and structural materials into the elevated temperature structural design guide for fast breeder reactors (FBRs), research and development of sodium compatibility of the materials has been performing in Japan Atomic Energy Agency. This paper describes the overview of sodium compatibility of the candidate materials which are used as core and structures of Japanese demonstration FBRs.

Journal Articles

Bahavior of HTGR particle fuel under reactivity initiated accident condition

Umeda, Miki; Ueta, Shohei; Sugiyama, Tomoyuki

Transactions of the American Nuclear Society, 98(1), P. 987, 2008/06

Oral presentation

JSFR innovative design and its challenges to structural and fuel materials

Morishita, Masaki; Asayama, Tai; Inoue, Masaki; Kotake, Shoji; Mizuno, Tomoyasu

no journal, , 

JSFR is a sodium cooled loop type fast reactor on which a conceptual design study is now underway in the framework of "Fast Reactor Cycle Technology Development Project (FaCT Project)" of Japan. Achieving economic competitiveness with future light water reactors, along with assuring high level of safety and reliability, is among its most crucial development targets. In this paper described are the major design features of JSFR and related material development issues.

Oral presentation

Potential for international collaborations on closed fuel cycle demonstrations and implementations in JAEA

Funasaka, Hideyuki

no journal, , 

The following 3 subjects is introduced and discussed in this panel session of ANS Meeting. (1) Current status and perspective of Fast Reactor Cycle Technology Development Project. (2) Related facilities for closed fuel cycle demonstaration and implementation. (3) Existing collaborative agreements for fuel cycle development and potential for new collaboration in future.

Oral presentation

Development of high burn-up fuel with SiC matrix for gas-cooled fast reactor

Hinoki, Tatsuya*; Park, Y.*; Park, J.*; Miwa, Shuhei; Donomae, Takako

no journal, , 

Nitride fuel and oxide fuel are candidate for helium gas-cooled fast reactor to achieve thermal efficiency over 40%. The conceptual design of fuel, which consists of nitride fuel of around 50%, highly dense SiC matrix and porous SiC buffer layers is encouraged according to the eport for "Feasibility Study on Commercialized Fast Reactor Cycle System (FS)", Japan. However there is no technique to form dense SiC in the small gap between fuels with accurate arrangement of fuels. The objective of this work is to develop basic fabrication technique for the high burn-up fuel utilizing forming technique for highly dense NITE-SiC/SiC composites. The cylindrical fuel is proposed in this work instead of spherical fuel to achieve high dense fuel and accurate arrangement.

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