Search Results 1-20 of 500

  • Development of Neutronics and Thermal-hydraulics Coupled Analysis Method on Platform for Design Optimization in Fast Reactor  [in Japanese]

    堂田 哲広 , 浜瀬 枝里菜 , 横山 賢治 , 田中 正暁

    計算工学講演会論文集 Proceedings of the Conference on Computational Engineering and Science 25, 4p, 2020-06

  • Thermal-Hydraulic Research in View of Nuclear Safety  [in Japanese]

    三島 嘉一郎

    … Concerning thermal-hydraulics research, severe accident research in particular, the question arises whether or not research results were reflected to safety measures or those obtained deserved it. … In view of these, thermal-hydraulics research concerning nuclear safety up to the present will be reviewed and some suggestions will be presented in this paper. …

    社会安全学研究 = Safety science review (10), 85-96, 2020-03-31

    IR 

  • Analytical Functions and Development Status of the System Analysis Code for Nuclear Power Plants, AMAGI  [in Japanese]

    KANEKO Junichi , TSUKAMOTO Naofumi

    … The thermal hydraulic model, heat conduction model, control model, and thermal power model were implemented into AMAGI as primary analytical functions. …

    Transactions of the Atomic Energy Society of Japan 19(3), 163-177, 2020

    J-STAGE 

  • Preliminary analysis of sodium experimental apparatus PLANDTL-2 for development of evaluation method for thermal-hydraulics in reactor vessel of sodium fast reactor under decay heat removal system operation condition

    ONO Ayako , TANAKA Masaaki , MIYAKE Yasuhiro , HAMASE Erina , EZURE Toshiki

    … It is needed to grasp the thermal-hydraulic phenomena in the reactor vessel and evaluate the coolability of the core under the natural circulation not only for the normal operating condition but also for severe accident conditions. … The steady-state analysis coinciding Richardson number between the PLANDTL-2 and the reactor operation condition reveals that the hot spot and cold spot appear depending on the location of the DHX, which is caused by the complex thermal-hydraulic phenomena driven by the natural circulation. …

    Mechanical Engineering Journal 7(3), 19-00546-19-00546, 2020

    J-STAGE 

  • Advancement of elemental analytical model in LEAP-III code for tube failure propagation

    UCHIBORI Akihiro , YANAGISAWA Hideki , TAKATA Takashi , LI Jiazhi , JANG Sunghyon

    … This method consists of the elemental analytical models for a sodium-side temperature distribution formed by a reacting jet, water-side thermal hydraulics, heat transfer between a fluid and a tube, and tube failure by internal pressure. …

    Mechanical Engineering Journal 7(3), 19-00548-19-00548, 2020

    J-STAGE 

  • Numerical simulation of two-phase flow in 4x4 simulated bundle

    ONO Ayako , YAMASHITA Susumu , SUZUKI Takayuki , YOSHIDA Hiroyuki

    … <p>An evaluation methodology of a thermal-hydraulics based on a mechanism in light water reactors (LWRs) is needed from a viewpoint of the safety analysis during normal operation and unanticipated transient such as under a severe accident. … Moreover, JAEA is implementing the development of the nuclear-thermal-coupling code by using a detailed two-phase flow analysis code based on the VOF method like a JUPITER code. …

    Mechanical Engineering Journal 7(3), 19-00583-19-00583, 2020

    J-STAGE 

  • Gas-Liquid Two-Phase Flow Image Analysis Using Bubble Detection Algorithm  [in Japanese]

    TORISAKI Shuhei , MIWA Shuichiro

    … One of its unique characteristics is the presence of flow regime, and its identification is crucial for improving the accuracy of thermal-hydraulic analysis codes as well as securing the integrity of piping systems. … By utilizing the current tool, instant objective two-phase flow feature extraction is now possible, and our results showed promising performance by coupling the state-of-the-art AI technique with conventional thermal-hydraulics.</p> …

    JAPANESE JOURNAL OF MULTIPHASE FLOW 34(1), 125-133, 2020

    J-STAGE 

  • Thermal Hydraulics and Operating Criteria of Ultra-Micro Steam Injector  [in Japanese]

    FUTSUTA Akihiro , KANEKO Akiko , ABE Yutaka , SUZUKI Yutaka

    … The objective of the present study is to clarify thermal hydraulics characteristics and operating criteria for an Ultra-Micro Steam Injector. …

    JAPANESE JOURNAL OF MULTIPHASE FLOW 34(1), 36-45, 2020

    J-STAGE 

  • Development of numerical analysis code LEAP-III for tube failure propagation  [in Japanese]

    UCHIBORI Akihiro , YANAGISAWA Hideki , TAKATA Takashi , OHSHIMA Hiroyuki

    … This method consists of the elemental analysis models for a sodium-side temperature distribution formed by a reacting jet, water-side thermal hydraulics, heat transfer of a tube, and tube failure by internal pressure. …

    Transactions of the JSME (in Japanese) 86(883), 19-00353-19-00353, 2020

    J-STAGE 

  • Research and Development of Liquid Hydrogen-Cooled Superconducting Energy Apparatus  [in Japanese]

    SHIRAI Yasuyuki , SHIOTSU Masahiro

    … For this purpose, we have designed and constructed basic experimental facilities, such as a thermal-hydraulics experimental system for LH<sub>2</sub>, in order to carry out systematic investigation of the forced-flow heat transfer, set up experiments for investigating the electro-magnetic properties of superconductors or superconducting magnets, and introduced an LH<sub>2</sub> …

    TEION KOGAKU (Journal of Cryogenics and Superconductivity Society of Japan) 55(1), 44-52, 2020

    J-STAGE 

  • Thermal-Hydraulic Research in View of Nuclear Safety  [in Japanese]

    三島 嘉一郎

    社会安全学研究 = Safety science review (10), 85-96, 2019

  • Ultrasonic behavior on solidification of sodium chloride solution:-Construction of acoustic phase diagram-  [in Japanese]

    YOSHIOKA Hideaki , KYODEN Tomoaki , HACHIGA Tadashi

    <p></p><p>相変化スラリーの相変化量と熱流動を音速情報に基づき"視える化"することを目標に,水溶液の相変化過程と音響特性との連関について追究した.まず,超音波の簡易計測システムを構築し,塩化ナトリウム水溶液を供試して初期組成を変化させた凝固実験を行った.次いで,液相域・マッシュ域・固相域の各領域における音速変化を相変化過程と関連づけて特徴づけ,従来の温度 …

    Transactions of the Japan Society of Refrigerating and Air Conditioning Engineers 36(4), 291, 2019

    J-STAGE 

  • Prospects based on T-H Roadmap through Communication  [in Japanese]

    Nakamura Hideo

    Journal of the Atomic Energy Society of Japan 61(4), 270-272, 2019

    J-STAGE 

  • Japanese T-H:A Small Step Towards Giant Leap  [in Japanese]

    Miwa Shuichiro

    Journal of the Atomic Energy Society of Japan 61(4), 273-275, 2019

    J-STAGE 

  • Beam Window Design for Accelerator-Driven System  [in Japanese]

    SUGAWARA Takanori , EGUCHI Yuta , OBAYASHI Hironari , IWAMOTO Hiroki , TSUJIMOTO Kazufumi

    The Proceedings of Mechanical Engineering Congress, Japan 2019(0), S08111, 2019

    J-STAGE 

  • PRELIMINARY ANALYSIS OF SODIUM EXPERIMENTAL APPARATUS PLANDTL-2 FOR DEVELOPMENT OF EVALUATION METHOD FOR THERMAL HYDRAULICS IN REACTOR VESSEL OF SODIUM FAST REACTOR UNDER DECAY HEAT REMOVAL SYSTEM OPERATION CONDITION

    ONO Ayako , TANAKA Masaaki , MIYAKE Yasuhiro , HAMASE Erina , Ezure Toshiki

    … It is needed to grasp the thermal-hydraulic phenomena in the reactor vessel and evaluate the coolability of the core under the natural circulation for not only the normal operating condition but also severe accident condition. …

    The Proceedings of the International Conference on Nuclear Engineering (ICONE) 2019.27(0), 2318, 2019

    J-STAGE 

  • IN-VESSEL THERMAL-HYDRAULICS ANALYSES OF THE ASTRID-600MWE REACTOR WITH STAR-CCM+ CODE TO SUPPLY BOUNDARY CONDITIONS FOR MECHANICAL EVALUATION

    ONODA Yuichi , CHIKAZAWA Yoshitaka , NAKAMURA Hironori , BARBIER Dominique , DIRAT Jean-François

    … In order to perform mechanical analyses for this component expected lifetime and in accordance with the French RCCMrX code, it is necessary to identify the most penalizing thermal-hydraulics transients. … In the case of Loss of Grid and because of thermal stratifications due to lower flow rate, a reverse of surface temperatures appears on the inner vessel which is much more detrimental for the structures thermomechanical behavior. …

    The Proceedings of the International Conference on Nuclear Engineering (ICONE) 2019.27(0), 2239, 2019

    J-STAGE 

  • EFFECT OF SUPPRESSION POOL CONDITIONS ON RISING BUBBLE PARAMETERS DURING WETWELL VENTING

    Zablackaite Giedre , Nagasaka Hideo , Takahashi Hideharu , Kikura Hiroshige

    … One of the important factors became the containment thermal hydraulics and aerosol transport. … Thermal stratification and depressurization may influence steam and non-condensable gas carrying FPs bubble hydrodynamics while bubbles are rising through the pool. … Therefore, data base of bubble diameter and bubble rising velocity under thermal stratification and depressurization conditions is important for the improvement of Pool scrubbing code hydrodynamic models. …

    The Proceedings of the International Conference on Nuclear Engineering (ICONE) 2019.27(0), 2300, 2019

    J-STAGE 

  • Development of Numerical Analysis Code LEAP-III for Tube Failure Propagation  [in Japanese]

    UCHIBORI Akihiro , YANAGISAWA Hideki , TAKATA Takashi , OHSHIMA Hiroyuki

    … This method consists of the elemental analysis models for a sodium-side temperature distribution formed by a reacting jet, water-side thermal hydraulics, heat transfer of a tube, and tube failure by internal pressure. …

    The Proceedings of the National Symposium on Power and Energy Systems 2019.24(0), B122, 2019

    J-STAGE 

  • Evaluation of Internal Multiphase Flow Field using Artificial Intelligence  [in Japanese]

    MIWA Shuichiro

    Two-phase flow regime identification in internal flow system is crucial for various energy systems involving phase-change. Closure of several conservation equations often times require proper selectio …

    The Proceedings of the National Symposium on Power and Energy Systems 2019.24(0), B222, 2019

    J-STAGE 

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