Search Results 1-20 of 246

  • A SUMMARY OF TRITIUM BEHAVIOR IN NUCLEAR POWER PLANTS

    Lou Mengqi , Li Wenqian , Guo Chao , Li Peng , Xie Feng , Wang Yu

    … The sources and proportions of tritium in light water reactors (LWRs), heavy water reactors (HWRs), high temperature gas-cooled reactors (HTGRs), and liquid metal fast breeder reactors (LMFBRs) are investigated and comprehensively compared. … The discharge standards of the liquid and gaseous effluent on tritium among different countries are also presented, which may provide suggestions on the tritium treatment and disposal in future. …

    The Proceedings of the International Conference on Nuclear Engineering (ICONE) 2019.27(0), 1594, 2019

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  • The development status of Generation IV reactor systems(6):Molten salt reactor and thorium reactor  [in Japanese]

    Takaki Naoyuki

    <p> 新たな原子炉型として液体燃料を用いる溶融塩炉への関心が高まっている。これは特に,福島第一原発事故以降に顕著だが,エネルギー消費大国に成長した中国は福島事故の数ヶ月前,将来の商業化を目指した大規模な溶融塩炉開発計画を立ち上げた。日本国内とはやや温度差があるが,世界各国では中国の動きに触発されたかのようにその後溶融塩炉研究が活発化している。本稿では第4世代原子炉の一つである溶融塩炉 …

    Journal of the Atomic Energy Society of Japan 60(8), 493-498, 2018

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  • Research frontier of tritium for fusion reactor-toward the DEMO reactor-(5):Research frontiers of liquid breeders for fusion reactors  [in Japanese]

    Kondo Masatoshi , Tanaka Teruya

    <p> 核融合炉の燃料増殖ブランケットに不可欠な機能を全て兼ね備えている液体増殖材の開発研究が着実に進展している。液体増殖材の実用上の課題として,材料共存性の改善やトリチウム輸送制御法の確立が挙げられるが,これらは液体増殖材の流動性がもたらす特殊な界面反応や輸送的性質によるものである。しかし,高度な純度制御技術が開発された事により,材料共存性改善の糸口が見える状況になってきた。また,斬 …

    Journal of the Atomic Energy Society of Japan 60(11), 700-704, 2018

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  • Current Status of Studies on Liquid Blanket Systems  [in Japanese]

    TANAKA Teruya , NORIMATSU Takayoshi

    核融合ブランケットは核融合炉の炉心を取り囲むように設置される発電用大型コンポーネントであり,中性子エネルギーから熱エネルギーへの変換,放射線遮蔽に加えて,自然界に存在しないトリチウム燃料の生産を担う.このトリチウム生産のために,リチウム原子を含む液体金属や溶融塩といった高温融体(液体)をトリチウム増殖材としてブランケット内に配置するものを特に"液体ブランケット"という.設計や材料組み合せによるが, …

    プラズマ・核融合学会誌 92(2), 112-118, 2016-02

    NDL Digital Collections 

  • Experimental Study on Chemical Behaviors of Non-Metal Impurities in Pb, Pb-Bi and Pb-Li by Temperature Programmed Desorption Mass Spectrometer Analysis

    KONDO Masatoshi , NAKAJIMA Yuu , TANAKA Teruya , NOZAWA Takashi , YOKOMINE Takehiko

    <p>The chemical behaviors of non-metal impurities such as O<sub>2</sub>, H<sub>2</sub>, N<sub>2</sub>, H<sub>2</sub>O, CO<sub>2 </sub> …

    Plasma and Fusion Research 11(0), 2405076-2405076, 2016

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  • A study on plastic strain accumulation caused by traveling of temperature distribution synchronizing with temperature rise

    OKAJIMA Satoshi

    … The prevention of excessive deformation by thermal ratcheting is important in the design of high-temperature components of fast breeder reactors (FBR). … This includes evaluation methods for a new type of thermal ratcheting caused by an axial traveling of temperature distribution, which corresponds to moving-up of liquid sodium surface in startup phase. … In the actual application, we can control the plastic deformation range by changing rate of the moving-up of liquid sodium surface. …

    Mechanical Engineering Journal 3(3), 15-00574-15-00574, 2016

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  • <i>In-Situ</i> Evaluation of Functional Layer by Electrochemical Impedance Spectroscopy  [in Japanese]

    Suzuki Narumi , Sasaki Ryosuke , Matsumura Yoshihito , Kondo Masatoshi

    …  Online evaluation of the electrical properties of oxide layers was studied for the development of liquid breeder blanket of fusion reactors in this paper. …

    Journal of the Japan Institute of Metals and Materials 80(4), 284-288, 2016

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  • ICONE23-2059 NUMERICAL ANALYSIS OF THERMAL HYDRAULIC BEHAVIOR BASED ON TWO-FLUID MODEL DURING INGRESS OF COOLANT EVENT IN BLANKET MODULE

    Ose Yasuo , Tanigawa Hisashi , Kawamura Yoshinori

    … For water-cooled ceramic breeder blankets in fusion reactors, neutron multiplier materials such as beryllium are packed into the blankets to obtain tritium breeding capability. … The results showed that the void fraction, the pressure and the liquid temperature in the cooling pipe increased caused by the vaporization of coolant during the ICE. … As a result, it is concluded that the modified TRAC-PF1 code is useful as a safety analysis for the ceramic breeder blanket. …

    The Proceedings of the International Conference on Nuclear Engineering (ICONE) 2015.23(0), _ICONE23-2-_ICONE23-2, 2015

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  • ICONE23-1505 SAFETY REQUIREMENTS EXPECTED FOR THE PROTOTYPE FAST BREEDER REACTOR "MONJU"

    SAITO Shinzo , OKAMOTO Koji , KATAOKA Isao , SUGIYAMA Ken-ichiro , MURAMATSU Ken , ICHIMIYA Masakazu , KONDO Satoru , YONOMOTO Taisuke

    … consisting of fast breeder reactor (FBR) and safety assessment experts in order to establish original safety requirements expected for the prototype FBR "Monju" … Liquid sodium can be used in the wide temperature range and natural circulation could be rather easily formed. …

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

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  • ICONE23-1467 Behavior of Entrainment Droplet formed by High Velocity Air Jet Flow in Stagnant Water

    Akabane Masaaki , Horiki Sachiyo , Osakabe Masahiro , Koizumi Yasuo , Uchibori Akihiro , Ohno Shuji , Ohshima Hiroyuki

    … A sodium-cooled fast breeder reactor (FBR) is now in a developing stage in Japan. … Water-sodium chemical reaction results an increase the entrained liquid droplet temperature. … The hot and high speed sodium entrained liquid droplets attack the wall of a neighboring tube to damage and create a hole on the tube wall, which may result in the chain tube wall damage. …

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

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  • ICONE23-1183 A STUDY ON PLASTIC STRAIN ACCUMULATION CAUSED BY TRAVELING OF TEMPERATURE DISTRIBUTION SYNCHRONIZING WITH TEMPERATURE RISE

    OKAJIMA Satoshi

    … The prevention of excessive deformation by thermal ratcheting is important in the design of high-temperature components of fast breeder reactors (FBR). … This includes evaluation methods for a new type of thermal ratcheting caused by an axial traveling of temperature distribution, which corresponds to moving-up of liquid sodium surface in startup phase. …

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

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  • The Current Status of the World ITER Test Blanket Module Program  [in Japanese]

    KONISHI Satoshi , ENOEDA Mikio

    ITER/TBM計画は,核燃焼プラズマ環境において,燃料トリチウムの増殖回収と,高品質熱エネルギーへの変換取り出しを実証し,またその性能を評価することを目的としており,ITERにおける研究の主要目的の一つである.国際共同作業で一つの装置を共有する燃焼プラズマ実験と異なり,各参加極が,異なる概念・構造のブランケットモジュールを持ち寄り,それぞれに異なる次期計画に向けて試験を行う,国際競争の面をもつ. …

    プラズマ・核融合学会誌 90(6), 332-337, 2014-06

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  • Integrated Material System Modeling of Fusion Blanket

    SAGARA A. , NYGREN R. , MIYAMOTO M. , NISHIJIMA D. , DOERNER R. , FUKADA S. , OYA Y. , ODA T. , WATANABE Y. , MORISHITA K. , GAO F. , NORIMATSU T.

    … In this paper, we review the main outputs of this task: elucidation of the effect of helium on deuterium retention in the tungsten wall, analysis of tritium transfer in a Pb–Li liquid breeder, experimental and computational studies on the effects of radiation damage on hydrogen trapping, and modeling of the tritium barrier in a double-tube heat exchanger. …

    MATERIALS TRANSACTIONS 54(4), 477-483, 2013-04-01

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  • Heat-Pulse Flowmeter for a Liquid Breeder Blanket

    KONDO Masatoshi , SHIBANO Kyohei , TANAKA Teruya , MUROGA Takeo

    Liquid metals Li, Pb-17Li and Sn-20Li are candidate liquid breeders in fusion reactors. … The development of a flowmeter that can be applied to high-temperature liquid metals is an important issue. …

    Plasma and Fusion Research 8(0), 2405086-2405086, 2013

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  • Hydrogen absorption and desorption behavior of liquid tritium breeding materials monitored with metal permeation windows  [in Japanese]

    Yagi Juro , Watanabe Takashi , tanaka Teruya , Muroga Takeo , Sagara Akio

    金属透過窓を利用して液体トリチウム増殖材の水素吸収・放出特性を測定している。リチウム鉛やFlinak溶融塩といった既存の材料に加え、リチウムナトリウム合金などの新組成の材料探索にも利用できる体系を構築し利用した。透過窓材料は各材料との両立性を勘案して異なる材料を選定している。類似概念での試験は報告例があるが、本研究では水素透過の上流側・下流側両面に透過窓を採用した自由表面を有さない体系となっている …

    Proceedings of Annual / Fall Meetings of Atomic Energy Society of Japan 2013s(0), 573, 2013

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  • Development of maintenance technology for advanced fast breeder reactor applicationDevelopment of maintenance technology for advanced fast breeder reactor application:4. Cavitation erosion in liquid metal  [in Japanese]

    Hattori Shuji , Kobayashi Yuya , Nimura Akihiro , Yada Hiroki

    次世代高速増殖炉では,冷却系をもんじゅの3ループから2ループに減少させるために流速が10m/s程度に高くなり,配管内にキャビテーションが発生して配管壁面に損傷を与える可能性がある.本研究では,磁わい振動試験による液体金属中のキャビテーション壊食に及ぼす液温及び振幅の影響を明らかにした.また,キャビテーションの発生する下限界値を検出する方法及び壊食速度の振幅依存性を基に流速依存性を検討した.

    Proceedings of Annual / Fall Meetings of Atomic Energy Society of Japan 2013s(0), 205, 2013

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  • Study on Pb-17Li natural convection loop and heat pulse flow meter  [in Japanese]

    Kondo Masatoshi , Shibano kyouhei , Tanaka Teruya , Muroga Takeo

    インベントリー780㏄の自然対流ループに鉛リチウムを充填し、 循環試験を実施した。更に、これまでに小型実験装置において課題であった 流速測定に関して、ヒートパルス流速測定法を導入し、その適合性について 実験とシミュレーションの両方から考察した。

    Proceedings of Annual / Fall Meetings of Atomic Energy Society of Japan 2013s(0), 575, 2013

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  • Effect of Sodium on Repair-Weldability of SUS316FR for Fast Breeder Reactor  [in Japanese]

    CHUN Eun Joon , BABA Hayato , NISHIMOTO Kazutoshi , SAIDA Kazuyoshi

    … According to the thermodynamic calculation, the sodium would expand the solid-liquid coexistence temperature range. … It could be concluded that the enhanced solidification cracking susceptibility under sodium environment would be attributed to the enlargement of the solid-liquid coexistence temperature range. …

    QUARTERLY JOURNAL OF THE JAPAN WELDING SOCIETY 31(4), 260-271, 2013

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  • High Cycle Fatigue Properties of Mod.9Cr-1Mo Steel at Elevated Temperatures  [in Japanese]

    NONAKA Isamu , NEMOTO Junpei , ICHIKAWA Yuji , MIURA Hideo

    … On the other hand, Mod.9Cr-1Mo steel is also a candidate material for demonstration fast breeder reactor in Japan. … A flow induced vibration is assumed in the piping due to the coolant liquid sodium flowing with high velocity inside the pipe. …

    Journal of the Society of Materials Science, Japan 62(2), 105-109, 2013

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  • 20812 Influence of Fragmentation Behavior on Molten Material Jet Breakup  [in Japanese]

    IWASAWA Yuzuru , NARIAI Hideki , ABE Yutaka , KANEKO Akiko , Kuroda TAIHEI , MATSUO Eiji , SAKABA Hiroshi , KOYAMA Kazuya , ITOH Kazuhiro , EBIHARA Kenichi

    … For the safety design of a Fast Breeder Reactor (FBR), Post Accident Heat Removal (PAHR) is required when a hypothetical Core Disruptive Accident (CDA) occurs. … The jet breakup and fragmentation behavior of the molten material and the transparent liquid are observed with a high speed video camera. …

    The Proceedings of Conference of Kanto Branch 2013.19(0), 419-420, 2013

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