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Journal Articles

Safety demonstration tests using High Temperature Engineering Test Reactor (HTTR)

Tachibana, Yukio; Nakagawa, Shigeaki; Iyoku, Tatsuo

Proceedings of International Conference on Global Environment and Advanced Nuclear Power Plants (GENES4/ANP 2003) (CD-ROM), 8 Pages, 2003/09

no abstracts in English

Journal Articles

Subchannel analysis of CHF experiments for tight-lattice core

Nakatsuka, Toru; Tamai, Hidesada; Kureta, Masatoshi; Okubo, Tsutomu; Akimoto, Hajime; Iwamura, Takamichi

Proceedings of International Conference on Global Environment and Advanced Nuclear Power Plants (GENES4/ANP 2003) (CD-ROM), 6 Pages, 2003/09

It is important to evaluate thermal margin of the tight lattice core in the Reduced-Moderation Water reactor (RMWR). In the present study, to assess the applicability of subchannel analysis for tight lattice cores, tight lattice CHF experiments were analyzed with COBRA-TF code. For the axial uniform heated rod bundle, the code gives good prediction of critical power for mass velocity of around 500kg/(m$$^{2}$$s), while the code underestimates it for lower mass velocity and overestimates for higher mass velocity. The predicted BT position was outer channels and differed from the measured position. For the axially double-humped heated bundle, the code gives good prediction for mass velocity of around 200kg/(m$$^{2}$$s), and overestimates for higher mass velocity. It turned out that the two-phase multiplier of friction loss have a large influences on the flow distribution among the subchannels. To improve the calculation accuracy, it is required to predict precisely the flow distribution including the prediction of pressure distribution in a tight lattice bundle.

Journal Articles

The High temperature gas cooled reactor fuel

Sawa, Kazuhiro; Ueta, Shohei; Iyoku, Tatsuo

Proceedings of International Conference on Global Environment and Advanced Nuclear Power Plants (GENES4/ANP 2003) (CD-ROM), 10 Pages, 2003/09

This paper provides present status of research and development for the coated fuel particle (CFPs) including the advanced ZrC-CFP. Current HTGR employs so-called TRISO-CFPs with SiC layer. In safety design of the HTGR fuels, it is important to retain fission products within CFPs so that their release to primary coolant does not exceed an acceptable level. The behavior of TRISO-CFPs has been investigated through experiments and reactor operation. These data show excellent performance of the TRISO-CFPs when they are correctly fabricated. On the other hand, the crystalline material comprising the SiC layer has a tendency to decompose at high temperature. The transition temperatures of beta-SiC (as-deposited) to alpha-SiC vary from 1600 to 2200$$^{circ}$$C. ZrC is one of the transition metal carbides which are characterized by the high melting point and the thermodynamic stability etc. The CFPs with CVD-ZrC coatings have been investigated including the fabrication processes and characterization techniques developments.

Journal Articles

Direct numerical simulation on fluid flow characteristics in a tight-lattice fuel bundle

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

Proceedings of International Conference on Global Environment and Advanced Nuclear Power Plants (GENES4/ANP 2003) (CD-ROM), 8 Pages, 2003/09

no abstracts in English

Journal Articles

Design Study on Sodium Cooled Fast Reactor Core Loaded with LLFP Transmutation Sub-Assemblies

Takaki, Naoyuki; Mizuno, Tomoyasu

GENES/ANP2003 NO1169, 0 Pages, 2003/00

A 1500MWe sodium-cooled MOX fuel core loaded with LLFP sub-assemblies has been studied. The LLFP sub-assembly contains either iodine compound pins or technetium metal pins with zirconium-hydride pins as neutron moderator to improve the transmutation capab

Journal Articles

Design study on Reduced-Moderation Water Reactor (RMWR) core for plutonium multiple recycling

Okubo, Tsutomu; Iwamura, Takamichi; Takeda, Renzo*; Yamauchi, Toyoaki*; Okada, Hiroyuki*

Proceedings of International Conference on Global Environment and Advanced Nuclear Power Plants (GENES4/ANP 2003) (CD-ROM), 8 Pages, 2003/00

A water-cooled reactor concept named Reduced-Moderation Water Reactor is under development for effective fuel utilization through plutonium multiple recycling based on the water-cooled reactor technology. The reactor aims at achievement of a high conversion ratio more than 1.0 with MOX fuel. Especially, the core performances during the Pu multiple recycling have been investigated for the advanced fuel reprocessing schemes with low decontamination factors than the current PUREX process, and are shown to achieve the conversion ratio more than 1.0 and the negative void reactivity coefficient.

Journal Articles

The Pressure tube inspection and integrity evalution in Fugen

Ishizuka, Nobuo; Takayama, Koichi; Nakai, Kozo

Proceedings of International Conference on Global Environment and Advanced Nuclear Power Plants (GENES4/ANP 2003) (Internet), 0 Pages, 2003/00

None

Journal Articles

LMFBR Design and its Evolution, 4; An Innovative Concept of Sodium-Cooled Middle-Scale Modular Reactor Pursuing High Economic Competitiveness

; ; Konomura, Mamoru; Toda, Mikio*

Proceedings of International Conference on Global Environment and Advanced Nuclear Power Plants (GENES4/ANP 2003) (Internet), 8 Pages, 2003/00

None

Journal Articles

LMFBR Design and its Evolution, 2; Core Design of LMFBR

Mizuno, Tomoyasu; Uto, Nariaki; Takaki, Naoyuki

Proceedings of International Conference on Global Environment and Advanced Nuclear Power Plants (GENES4/ANP 2003) (Internet), 0 Pages, 2003/00

Sodium-cooled core design studies are performed. MOX fuel core with axial blanket partial elimination subassembly due to safety consideration is studied. This type of core with high internal conversion ratio possesses capability of achieving 26 months of

Journal Articles

LMFBR Design and its Evolution, 1; Fuel Design of LMFBR

; Naganuma, Masayuki

Proceedings of International Conference on Global Environment and Advanced Nuclear Power Plants (GENES4/ANP 2003) (Internet), 5 Pages, 2003/00

Corrent LMFBR fuel design study for future sysytem in Japan aims at achieving high burnup and high outlet temperature to get advantage of economic and resource utilization. Primary fuel integrity limiting features of such design study are core material

Journal Articles

The Current status of R&D for accelerator-driven system at JAERI

Sasa, Toshinobu; Oigawa, Hiroyuki; Tsujimoto, Kazufumi; Nishihara, Kenji; Umeno, Makoto*; Takano, Hideki*

Proceedings of International Conference on Global Environment and Advanced Nuclear Power Plants (GENES4/ANP 2003) (CD-ROM), 8 Pages, 2000/09

Japan Atomic Energy Research Institute (JAERI) performs research and development for accelerator-driven transmutation systems to improve the environmental impact and increase a capacity of waste disposal plant. The system consists of a superconducting proton LINAC, Pb-Bi eutectic spallation target and Pb-Bi cooled subcritical core. Thermal output of the system is 800MW by injection of the proton beam with the power of 20 to 30MW and then, about 250kg of minor actinides can be transmuted annually. To study and evaluate the feasibility of ADS by a physical and an engineering viewpoint, the Transmutation Experimental Facility is proposed under a framework of J-PARC project. In the presentation, the R&D activities by the contract between the Ministry of Education, Culture, Sports, Science and Technology will be presented.

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