Search Results 1-20 of 233

  • Development of Nuclear Powered Spaceship with SMR-Type FBR and Stirling Engine Power Generating System  [in Japanese]

    NARABAYASHI Tadashi

    … We selected the SMR type fast reactor system of about 18 MWth compared with other type of reactors, such as PWR and high temperature gas reactor. …

    The Proceedings of the National Symposium on Power and Energy Systems 2019.24(0), B114, 2019

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  • Development of portable laser peening systems for practical application  [in Japanese]

    CHIDA Itaru , SHIIHARA Katsunori , SUGANUMA Naotaka , UAGUCHI Kohei , IMASAKI Kazuto , ICHIKAWA Hiroya

    … Laser Peening (LP) technology was developed and applied to reactor components in operating Boiling Water Reactors (BWR) and Pressurized Water Reactors (PWR). … On the other hand, mirror-delivery type of LP tool was employed for outside surface of BMI nozzles. …

    The Proceedings of the National Symposium on Power and Energy Systems 2018.23(0), D112, 2018

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  • Design Concept of a Small Nuclear Reactor for Large-Diameter NTD-Si using Short PWR Fuel Assemblies

    Munkhbat Byambajav , Obara Toru

    … Design concept of a small reactor for NTD-Si was proposed using short PWR fuel assemblies. … PWR type fuel assemblies were used, thus the stable and reliable supply of the fuel can be expected because there are several PWR fuel manufacturers. …

    Proceedings of Annual / Fall Meetings of Atomic Energy Society of Japan 2012f(0), 774, 2012

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  • ICONE19-43646 A Study for Small-medium LWR Development of JAPC

    Okazaki Toshihiko , Hida Takahiko , Hoshi Takashi , Asano Hiromitsu , Kawahara Hiroto , Tominaga Kenji

    … In addition, large-sized reactors have an advantage of economy of scale and 1,000MWe LWR has therefore become the mainstream reactor in Japan. … Concepts have been developed for two types of SMRs (i.e. BWR and PWR). … As for the BWR type, reactor system is simplified by adopting natural circulation core method and CRD falling under gravity in order to downsize the reactor containments. …

    The Proceedings of the International Conference on Nuclear Engineering (ICONE) 2011.19(0), _ICONE1943-_ICONE1943, 2011

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  • ICONE15-10865 Total Energy Supply-System for Manned Spaceship using Nuclear Reactor

    NARABAYASHI Tadashi , HONMA Yuji , YOSHIDA Yutaka , SHIMAZU Yoichiro

    … We selected the fast reactor system of about 18 MWth compared with other type of reactors, such as PWR and high temperature gas reactor (Honma, 2006). …

    The Proceedings of the International Conference on Nuclear Engineering (ICONE) 2007.15(0), _ICONE1510-_ICONE1510, 2007

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  • ICONE15-10054 WELDING REPAIR OF DEFECTS IN WWER REACTOR PRESSURE VESSELS

    Brumovsky Milan , Brynda Jiri , Ellinger Jiri

    … A wide experimental program was realized to propose, check and approve a procedure for repair of potential defects in underclad region of WWER-440 MWe (PWR type reactors of Russian design) reactor pressure vessels during operation. …

    The Proceedings of the International Conference on Nuclear Engineering (ICONE) 2007.15(0), _ICONE1510-_ICONE1510, 2007

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  • ICONE15-10053 NEW PROCEDURE TO ASSESS PTS FOR CLADDED WWER REACTOR PRESSURE VESSELS

    Brumovsky Milan , Pistora Vladislav , Lauerova Dana , Neuvonen Alpo , Kohopaa Jyrki , Kim Wallin

    … WWER (PWR type reactors of Russian design) reactor pressure vessels are characterized by relatively thick austenitic cladding on their inner surface. … Existence of cladding results in high residual stresses in inner surface area and thus in high stress intensity coefficients of postulated/calculated under clad type defects. …

    The Proceedings of the International Conference on Nuclear Engineering (ICONE) 2007.15(0), _ICONE1510-_ICONE1510, 2007

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  • Strategic Considerations on Development of Nuclear Power and the Associated Fuel Cycle in China

    GU Zhongmao , LIU Changxin , FU Manchang

    Journal of Nuclear Science and Technology 43(9), 963-966, 2006-09-25

  • Analysis of High Moderation Full MOX BWR Core Physics Experiments BASALA

    ISHII Kazuya , ANDO Yoshihira , TAKADA Naoyuki , KAN Taro , SASAGAWA Masaru , KIKUCHI Tsukasa , YAMAMOTO Toru , KANDA Ryoji , UMANO Takuya

    … core, two homogeneous full MOX cores and one full MOX PWR mock-up core that have higher moderation ratio than the conventional lattice. …

    Transactions of the Atomic Energy Society of Japan 4(1), 45-65, 2005

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  • The Development and Validation of Standarized Main Control Boards for full digital PWR I & C system

    MAEDA Muneaki , TSUCHIYA Akiyoshi , TAMAGAWA Koichi , NAKANO Shunsuke , AOYAGI Toshihiro , YOKOYAMA Masanori , KOMATSUBARA Tadao , KITAMURA Masashi , IMASE Masahiro

    … To this end, Mitsubishi group and Japanese PWR utilities have been improving main control boards design for next PWR plants with full digital instrumentation and control system. …

    Transactions of the Atomic Energy Society of Japan 2(3), 307-318, 2003

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  • Analysis of MOX Core Physics Experiments MISTRAL

    ISHII Kazuya , TATSUMI Masahiro , KAN Taro , ANDO Yoshihira , YAMAMOTO Toru , IWATA Yutaka , UMANO Takuya , KANDA Ryoji

    … core, two homogeneous full MOX cores and one full MOX PWR mock-up core that have higher moderation ratio than the conventional lattice.<BR>NUPEC has been analyzing the experimental results with the diffusion and the transport calculations by the SRAC code system and the continuous energy Monte Carlo calculations by the MVP code with the common nuclear data file, JENDL-3.2. …

    Transactions of the Atomic Energy Society of Japan 2(1), 39-54, 2003

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  • Probabilistic Effectiveness Assessment of Severe Accident Management

    YOSHIDA Yoshitaka

    … This method was applied to evaluated the risk decreasing effect at a typical 4-loop PWR plant with a dry containment vessel, and analyzed the sensitivity of DME and UOE.<BR>As a result, (1) after the preparation of accident management, the containment failure frequency was 1.0×10<SUP>-8</SUP> …

    Transactions of the Atomic Energy Society of Japan 2(4), 428-451, 2003

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  • F310 DAMAGE PROBABILITY OF THE STEAM GENERATOR HEAT EXCHANGE PIPELINES IN VVER NPP

    Baranenko V. I. , Oleynik S. G. , Merkushev V. N. , Kostyukov O. E. , Belyakov O. A. , Kumov A. V.

    … Low operational reliability of steam generators (SG) of NPPs with VVER type reactors is one of main factors affecting stability and quality of the output electric energy. … Therefore the enhancement of SG operational reliability attracts attention of experts from the countries operating PWR and VVER NPPs. …

    The Proceedings of the International Conference on Power Engineering (ICOPE) 2003.3(0), _3-427_-_3-432_, 2003

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  • RETRAN Code Analysis of Tsuruga-2 Plant Chemical Volume Control System (CVCS) Reactor Coolant Leakage Incident

    KAWAI Hiroshi

    Journal of Nuclear Science and Technology 39(12), 1269-1274, 2002-12-25

    References (3)

  • Concept of Next Generation PWR (APWR+)

    MAKIHARA Yoshiaki , USUI Shuji

    … The plant concept of 1, 700 MWe class next generation PWR (APWR+) has been established. …

    Transactions of the Atomic Energy Society of Japan 1(4), 404-411, 2002

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  • Application of Passive Autocatalytic Recombiner (PAR) for BWR Plants

    KOBAYASHI Kei , KAMIZUMA Nobuaki , FUJIMOTO Kiyoshi , KARASAWA Hidetoshi , MURANO Kenji , MIYATA Koichi , MASUDA Takahiro , YAMAMOTO Yuji , HARADA Makoto , TAHARA Mika , OIKAWA Hirohide , YAMANARI Shouzou

    … This type of recombiner is already introduced to many PWR plants in the United States and Europe.<BR>In this situation, Japanese BWR utilities planned to introduce the passive autocatalytic recombiner to new plants to reduce the equipment and maintenance costs and improve system reliability by eliminating dynamic devices and support systems. …

    Transactions of the Atomic Energy Society of Japan 1(1), 80-89, 2002

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  • Conceptual Design of Steam Generator for IMR (Integrated Modular water Reactor) : Investigation of Tubular Steam Generators  [in Japanese]

    NISHIDA Kenji , HIRANO Hiroshi , MIZUTANI Toshiyuki , HIRAO Yasuhiko

    … The integrated Modular water Reactor (IMR), which is one of small sized water reactors, has Steam Generators in Liquid (SGL) area and in Vapor (SGV) area of the Reactor Vessel (RV) respectively. … As a result, a vertical type U-tube SG is selected for SGL, because of lower pressure drop and manufacturability by proven technology for current PWR SGs. …

    The Proceedings of the National Symposium on Power and Energy Systems 2002.8(0), 567-570, 2002

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  • High Moderation MOX Cores for Effective Use of Plutonium in LWRs.  [in Japanese]

    HAMAMOTO Kazuko , KANAGAWA Takashi , HIRAIWA Koji , SAKURADA Koichi , MORIWAKI Masanao , AOYAMA Motoo , YAMAMOTO Toru , UEJI Masao

    … The PWR cores studied have H/HM of 5.0 and 6.0 with reducing a fuel rod diameter based on a reference 17×17 fuel (H/HM=4.0) of APWR. …

    Journal of the Atomic Energy Society of Japan / Atomic Energy Society of Japan 43(5), 503-517, 2001

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  • Investigation of Irradiation Induced Inter-granular Stress Corrosion Cracking Susceptibility on Austenitic Stainless Steels for PWR by Simulated Radiation Induced Segregation Materials

    Yonezawa Toshio , Fujimoto Koji , Kanasaki Hiroshi , Iwamura Toshihiko , Nakada Shizuo , Ajiki Kazuhide , Urata Sigeru

    … An Irradiation Assisted Stress Corrosion Cracking (IASCC) has not been found in Pressurized Water Reactors (PWRs). … However, the authors have investigated on the possibility of IASCC so as to be able to estimate the degradation of PWR plants up to the end of their lifetime.<br>In this study, the authors melted the test alloys whose bulk compositions simulated the grain boundary compositions of irradiated Type 304 and Type 316CW stainless steels. …

    Zairyo-to-Kankyo 49(7), 437-444, 2000

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