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Akatsu, Minoru; Tozawa, Katsuhiro; Watanabe, Ichiro; Ichimiya, Masakazu; Hayashi, Hideyuki; Mukaibo, Ryuichi
PNC TN9430 96-005, 237 Pages, 1996/07
In 1995, a design study on the mixed-oxide fuel core of the large breeder reactor was done to realize actinide (including minor actinide) 600MWe recycle reactor plant aiming at minimization of the radioactive waste products at the view point of not only to lighten the burden of the environment but also to utilize efficiently the resources, Study was carried out and R&D items were clarified as to the following items, as plant system design. (1)influences to the plant system from decay heat increase. (2)reactor structure concept due to adoption ductless fuel assembly concept. The study results are as follows. The coolant flow pass concept to core assemblies and the core support concept were studied by taking account of ductless core system and the large floating force on core assemblies due to ductless core system, the features of the concepts were clarified and the mechanical hold down (MHD) mechanism concept was adopted against the floating force. The characteristics of the connection between the upper internal structure and the core assemblies were studied for the large eccentricity of the two structures due to installation error, thermal expansion difference, inclination of core assemblies, etc. The connection that were led by MHD was guessed to be done with no large problem by special connection procedure. The reactor auxiliary cooling system capacity of 16MW a loop is sufficient to remove core decay heat to maintain the integrity of the coolant boundary structure. The heat removal characteristics under natural convection circulation coolant flow is confirmed to be superior than ducted core plant because of the lower pressure drop property of the ductless core plant. The cask car type fuel handling system was selected as referenceex-vessel fuel handling system. Because the cask car type system was able to simplify the fuel handling system by the in-line configuration of fuel handling facilities. The decay heat of ductless spent fuel assembly in sodium pot ...
Kasai, Shigeo; Tozawa, Katsuhiro; Akatsu, Minoru; Ogawa, Shinta; Watanabe, Ichiro; Hayafune, Hiroki; Naganuma, Masayuki; Ichimiya, Masakazu; Hayashi, Hideyuki; Mukaibou, Ryuichi
PNC TN9430 96-004, 152 Pages, 1996/07
Authors are studying the Actinide Recycle Fast Breeder Reactor (named ARFBR in this paper), which contribute to the reduction of burdens to environments and to enhance the capability to prevent the nuclear proliferation as the entire nuclear recycle system (named Advanced Fuel Recycling FBR system (AFRFS) in this paper), and also investigating the ARTR for developing the ARFBR. The investigation of the ARTR consists of the design study of the ARTR and R&Ds of key technology existing in ARTR concept. The conceptual design study of the ARTR is planed to be conducted for 2 years from 1995 to 1996 as first stage. 1995's design study have been performed with drawing over all plant concept with supposing various tests in reactor and usage of reactor. Followings are distinctive feature of 1995's design study. (1)Maximum reactor power is 400MWt with about 1.6m diameter irradiation (burning) cores, which are designed to be operated up to 150GWd/t as average burn up. Maximum core diameter is about 2.5m for low power nuclear physics tests which are designed to be able to estimate characteristics of large scale core by using the test results. (2)Mixed oxide (MOX) and Mixed nitride (MN) core is designed respectively to be able to be used for static nuclear physics test, for nuclear and thermal transient test, and for full power irradiation or burning test. Each core is designed to terminate ATWS events passively, with using GEM for MOX core and with using spectral adjustment for MN core. (3)Fuel assembly is employed ductless type which is a promising candidate for the ARFBR. Sizing of a fuel assembly is determined in basis on MOX fuel design because MOX fuel pin length covers MN fuel pin which accommodates lesser FP gases because of its lower temperature. Fuel assembly is managed to be held by hydraulic force in case of freeing mechanical stopper by requirement of testability. (4)Reactor assembly is designed based on so called Head Access Loop Type Reactor. Main changes ...
Ando, Toshiro; Takatsu, Hideyuki; Nakamura, Hiroo; Yamamoto, Masahiro; ; Arai, Takashi; Kaminaga, Atsushi; ; Horiike, Hiroshi; Shimizu, Masatsugu; et al.
Kaku Yugo Kenkyu, 65(SPECIAL ISSUE), p.27 - 49, 1991/03
no abstracts in English
*; Takatsu, Hideyuki; Arai, Takashi; ; Kaminaga, Atsushi; Okubo, Minoru; *; *
JAERI-M 87-070, 44 Pages, 1987/05
no abstracts in English
Yamamoto, Masahiro; Shimizu, Masatsugu; Arai, Takashi; Nakamura, Hiroo; Ando, Toshiro; Ogiwara, Norio; Takatsu, Hideyuki; *; Okubo, Minoru; ; et al.
Nihon Genshiryoku Gakkai-Shi, 29(7), p.634 - 641, 1987/00
Times Cited Count：0 Percentile：0.02(Nuclear Science & Technology)no abstracts in English
