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Aoyama, Takafumi; Sekine, Takashi; Nakai, Satoru; Suzuki, Soju
Proceedings of 15th Pacific Basin Nuclear Conference (PBNC-15) (CD-ROM), 6 Pages, 2006/10
The experimental fast reactor JOYO is the first liquid sodium fast reactor in Japan. The purpose of constructing JOYO was to obtain technical information about liquid metal fast breeder reactors (LMFBR). In addition to providing operating experience, many kinds of irradiation tests have been conducted for the development of fuels and materials under the conditions of higher fast neutron flux and temperature than those in LWRs. JOYO has been operated successfully since its criticality was first achieved in 1977 without any serious problem, and this operation demonstrated the safety and reliability of the sodium cooled fast reactor. Continual facility improvements have been punctuated by major enhancements, the latest of which is MK-III. Compared to MK-II, MK-III has a four times larger irradiation capability, improved irradiation test vehicles and improved irradiation characterization. The applications of this enhanced capability include testing fuels and safety features for future FBRs, exploring use of fast reactors for transmutation of radioactive waste, and developing advanced materials for fusion power. In light of the shutdown of several fast reactors around the world, the ability to make such major contributions to reactor development takes on even greater significance. Irradiation tests, steady-state and safety related operations of JOYO are also expected to promote the development of JAEA's prototype FBR, Monju.
Kurisaka, Kenichi
Proceedings of 15th Pacific Basin Nuclear Conference (PBNC-15) (CD-ROM), 6 Pages, 2006/10
no abstracts in English
Lee, J.-K.; Naganuma, Masayuki
Proceedings of 15th Pacific Basin Nuclear Conference (PBNC-15) (CD-ROM), 6 Pages, 2006/10
Gas cooled Fast Reactor (GFR) is being researched as a candidate concept of Generation IV international Forum. As a main feature of GFR, it should be maintained high temperature and pressure of coolant gas for heat transfer efficiency. Present study assumed a cladding tube of fuel pin type reactor, and using of SiC/SiC composites. Thermal stress of cladding wall was estimated with a condition of linear heat rate and temperature. Through the present work, the ways to improve an applicability of SiC/SiC were clarified; they are the densification of matrix and the improvement of interphase in terms of fabrication. From the viewpoint of core design, the degradation of thermal conductivity by irradiation was identified as the most important factor. These results should be helpful not only to determine the geometries of core component but also to indicate the improvement direction of SiC/SiC.
Mihara, Takatsugu; Kotake, Shoji
Proceedings of 15th Pacific Basin Nuclear Conference (PBNC-15) (CD-ROM), 6 Pages, 2006/10
The economic competitiveness is one of the crucial points and has been emphasized in the design study of JSFR (JAEA Sodium Fast Reactor) concept. By employing innovative technologies for the NSSS cost reduction, and the complete passive Decay Heat Removal System that leads to BOP cost improvement, it is confirmed that the JSFR design concept is well suited to the development target equivalent to 1,000USD/kWe (as nth-of-a-kind, overnight cost). In this paper, the economical aspect in the JSFR design was summarized.
Nomura, Shigeo
no journal, ,
Tokai Reprocessing Plant (TRP) of JAEA was designed 1970s to reprocess nuclear spent fuel (NSF) mainly from domestic Light Water Reactors (LWR) and Advanced Thermal Reactor (ATR) "Fugen". It was necessary to challenge many requirements for steady operation of plant due to mechanical troubles in head-end process, acid corrosions of dissolver vessel and evaporator tubes, strict environmental restriction to release activity, and reduction of waste volume. Through these solutions, the maturity of current reprocessing technology was achieved. The next generation reprocessing system for Fast Reactor (FR) cycle will be industrialized by the best combination of innovative technologies from R&D efforts and the supporting technologies obtained by 30 years plant operation experiences.
Hamamoto, Shimpei; Sakaba, Nariaki
no journal, ,
no abstracts in English