Search Results 1-10 of 10

  • Visualization of inverted annular flow during reflooding phenomena by using neutron radiography  [in Japanese]

    SAITO Kei , AMI Takeyuki , UMEKAWA Hisashi , SAITO Yasushi , ITO Daisuke

    … <p>During the re-flooding process, the heat-transfer of inverted annular flow (IAF) plays an important role. …

    The Proceedings of Mechanical Engineering Congress, Japan 2018(0), S0820205, 2018


  • Three-dimensional Stress Analysis of Reflooding Tunnel during Submerging Process using Crack Tensor Model at Mizunami Underground Research Laboratory  [in Japanese]

    尾崎 裕介 , 松井 裕哉 , 桑原 和道 , 多田 浩幸 , 櫻井 英行 , 熊坂 博夫 , 郷家 光男 , 小林 伸司

    JAEA-research 2016(7), 巻頭1-2,1-125, 2016-06


    Oh Deog Yeon , Bang Young Seok , Seul Kwang Won , Woo Sweng Woong

    … Best-Estimate (BE) calculation is more broadly used in nuclear industries and licensing process to reduce the significant conservatism for evaluating Loss-of-Coolant-Accident (LOCA). … Six FEBA reflooding tests with the different initial and boundary conditions during reflood phase of L OCA, were chosen to quantify uncertainty ranges in the CIRCE method. …

    The Proceedings of the International Conference on Nuclear Engineering (ICONE) 2015.23(0), _ICONE23-1-_ICONE23-1, 2015


  • A223 Heat Transfer and Flow Characteristics during Reflooding Process in Natural Circulation Loop  [in Japanese]

    Kawai Takuya , Yumoto Ikki , Ami Takeyuki , Umekawa Hisashi , Ozawa Mamoru

    … Understanding of reflooding phenomena under oscillatory flow condition in natural circulation loop is required for the development of emergency core cooling system of a LWR, simplified BWR and so on. … In this investigation, the reflooding experiment was conducted with a natural circulation loop by using liquid nitrogen as working fluid. …

    The Proceedings of the Thermal Engineering Conference 2014(0), _A223-1_-_A223-2_, 2014



    Bachrata A. , Fichot F. , Repetto G. , Quintard M. , Fleurot J.

    … The understanding of the reflood process of a severely damaged reactor core represents a challenge in the prediction of safety margin of existing and future pressurized water reactors. … Currently, the French Institute of Radioprotection and Nuclear Safety (IRSN) has started two experimental programs, PRELUDE and PEARL, to investigate the physical phenomena during a reflood process at high temperature and to provide relevant data in order to improve predictive models. …

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


  • Heat Transfer Enhancement during Reflooding Process Using Radiation Induced Surface Activation  [in Japanese]

    Zhang Jian , Shimokawa Toshihisa , Yodo Tadakatsu , Mishima Kaichiro , Abe Hiroaki , Takamasa Tomoji

    本研究では、軽水炉事故時の燃料健全性評価の目安になっている燃料被覆管最高温度に大きな影響を及ぼす再冠水過程における伝熱性能について、放射線誘起表面活性(RISA)の効果による表面の濡れ性及び再冠水過程の熱伝達への影響を調べた。また、RISAのメカニズム解明のため、照射雰囲気のRISA効果への影響を調べた。その結果、γ線照射後は、ロッド表面の濡れ性が著しく向上し、リウェット開始時期が早まり、遷移沸領 …

    Proceedings of National Heat Transfer Symposium 2008(0), 28-28, 2008


  • OS8-9 Improvement of Wettability and Rewetting Characteristics of Heated Surface by Radiation Induced Surface Activation (RISA)  [in Japanese]

    ZHANG Jian , MISHIMA Kaichiro , HIROSE Yoshinori , HAZUKU Tatsuya , TAKAMASA Tomoji

    … In this study, reflooding experiments were performed on a vertical rod surface after γ-ray irradiation to improve wettability and rewetting characteristics of the heated surface by Radiation Induced Surface Activation (RISA) technology. … It was also indicated that during the quenching process, the wettability of the heated surface was varied seriously before and after the quenching, which indicated the unstable characteristics of the improved wettability of the surface by RISA effect. …

    The Proceedings of the National Symposium on Power and Energy Systems 2006.11(0), 219-222, 2006


  • Transient cooling process of fuel rod in reactivity initiated accident.

    MORI Michitsugu , TODA Saburo , OCHIAI Masa-aki , SAITO Shinzo

    … Out-of-pile experiments were performed with Zircaloy-4 rods in subcooled water envi-ronment to study the basic phenomena occurring in the transient cooling process undergone by a fuel rod during a reactivity-initiated accident (RIA) affecting a light water reactor (LWR). … The experimental results show that the cooling process of the fuel rod during an RIA can be divided into three phases separated by the quenching temperature <I>T<SUB>q</SUB></I> …

    Journal of Nuclear Science and Technology 17(6), 413-424, 1980


  • An Experimental Study on PWR-LOCA by ROSA-II, (IV):Severe Break Configuration in Hot Leg Break for Core Cooling during Blowdown  [in Japanese]

    ADACHI Hiromichi , SUZUKI Mitsuhiro , SOBAJIMA Makoto , OKAZAKI Motoaki , SHIBA Masayoshi

    … The major conclusions are as follows:<BR>(1) In a large break of hot leg piping, downward core flow at the early stage of blowdown process is weak and almost stagnant. … Therefore core cooling during reflooding process is better. …

    Journal of the Atomic Energy Society of Japan / Atomic Energy Society of Japan 20(5), 347-358, 1978


  • An Experimental Study on PWR-LOCA by ROSA-II, (II)  [in Japanese]

    SHIBA Masayoshi , ADACHI Hiromichi , OKAZAKI Motoaki , SOBAJIMA Makoto , SUZUKI Mitsuhiro , NAMATAME Ken

    … Chugging oscillation occurs while mixture level rises in the active core region.<br>(3) It is of considerable importance to note that in order to achieve effective core cooling during the long reflooding process, mixture level must be raised to the active core region before the core temperature becomes very high. …

    Journal of the Atomic Energy Society of Japan / Atomic Energy Society of Japan 19(6), 408-419, 1977


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