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全文: "片西"
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  • 大橋 一孝, 西原 哲夫, 國富 一彦, 中野 正明, 田沢 勇次郎, 岡本 太志
    日本原子力学会和文論文誌
    2008年 7 巻 1 号 32-43
    発行日: 2008年
    公開日: 2012/03/02
    ジャーナル フリー
      Interest on the development of the Very High Temperature Gas-Cooled Reactor (VHTR), of which the reactor outlet temperature is 950°C or much higher, has recently been increasing worldwide, and it was selected as one of the candidate reactor types in the Generation IV Reactor System International Forum. The Japan Atomic Energy Agency (JAEA) has already initiated R&D efforts on the electricity and hydrogen cogeneration plant with the VHTR system, GTHTR300C. Although the technical feasibility of the VHTR using pin-in-block fuel, which has already been used in the High-Temperature Engineering Test Reactor (HTTR), has been shown fundamentally, more improvements in core performances, such as a decrease in the occupational exposure doses during plant maintenance, are desired. This report presents the results of the conceptual core design study using multihole-type fuel and the study on the occupational exposure doses. The latter results show much better plant maintainability compared with the previous results on the GTHTR300.
  • 毛利 智聡, 西原 哲夫, 國富 一彦
    日本原子力学会和文論文誌
    2007年 6 巻 3 号 253-261
    発行日: 2007年
    公開日: 2012/03/07
    ジャーナル フリー
      Design studies of the hydrogen cogeneration high temperature gas cooled reactor (GTHTR300C), which can produce both on electric power and hydrogen, have proceeded in Japan Atomic Energy Agency. In future, it will be obliged to operate using not enriched uranium but plutonium to coexist with fast reactors after the full deployment of a fast reactor cycle. Therefore, a nuclear and thermal design has been performed to confirm the feasibility of the reactor core using Mixed-Oxide (MOX) fuel. The reactor core with operation period of 450days and average burn-up of 123 GWd/ton for discharged fuel was designed. The reactor core met safety requirements of the maximum fuel temperature of less than 1,400°C during normal operation, the maximum power density of less than 13 W/cm3, shutdown margin of more than 1.0%Δk/kk′ and negative reactivity coefficient. The results proved that it is possible to operate the GTHTR300C using MOX fuels without consuming natural uranium resources.
  • 池上 和律, 宇山 忠男, 尾崎 克彦, 片西 昌司, 里見 憲男, 徳永 道広, 永田 正義, 西川 雅弘, 東谷 恵市, 兵部 雅彦, 藤井 政治, 誉田 義英, 渡辺 健二
    春の分科会予稿集
    1982年 1982.4 巻
    発行日: 1982/03/15
    公開日: 2018/03/27
    会議録・要旨集 フリー
  • 池上 和律, 宇山 忠男, 尾崎 克彦, 片西 昌司, 里見 憲男, 徳永 道広, 永田 正義, 西川 雅弘, 東谷 恵市, 兵部 雅彦, 藤井 政治, 誉田 義英, 渡辺 健二
    春の分科会予稿集
    1982年 1982.4 巻
    発行日: 1982/03/15
    公開日: 2018/03/27
    会議録・要旨集 フリー
  • 日本原子力学会誌
    2003年 45 巻 10 号 0
    発行日: 2003年
    公開日: 2019/01/31
    ジャーナル フリー
  • 津上 英輔
    美学
    1993年 44 巻 3 号 62-
    発行日: 1993/12/31
    公開日: 2017/05/22
    ジャーナル フリー
  • 片西 昌司, 國富 一彦, 高田 昌二, 滝塚 貴和
    年次大会講演論文集
    2003年 2003.3 巻
    発行日: 2003/08/05
    公開日: 2017/08/01
    会議録・要旨集 認証あり
    JAERI has undertaken the design study of gas turbine high temperature reactor, the GTHTR300. The study aimed at development of a greatly simplified design that leads to substantially reduce technical and cost requirements for earlier deployment. The GTHTR300 is expected to be an economically competitive reactor in 2010s due to newly proposed design features such as reactor core with two-year refueling interval, conventional steel material usage for a reactor pressure vessel, innovative plant flow scheme and horizontally installed gas turbine unit. This paper describes the original design features focusing on designs of reactor core, power conversion system, component technology developments and operation and control method. In the fiscal year 2002,modification was conducted for many facility designs and the higher safety margin and improved reactor characteristics were obtained.
  • 武井 正信, 小杉山 真一, 毛利 智聡, 片西 昌司, 國富 一彦
    日本原子力学会和文論文誌
    2006年 5 巻 2 号 109-117
    発行日: 2006/06/25
    公開日: 2010/01/21
    ジャーナル フリー
    Japan Atomic Energy Research Institute (JAERI) has been developing a graphite moderate and helium cooled High Temperature Gas-cooled Reactor (HTGR) with gas turbine, the GTHTR300 based on experience gained in development and operations of the High Temperature Engineering Test Reactor (HTTR) in JAERI. The GTHTR300 is a simplified and economical power plant with a high level of safety characteristics and a high plant efficiency of approximately 46%. Cost evaluation for plant construction and power generation is studied in order to clarify the economical feasibility of the GTHTR300. The construction cost is estimated to be about 200 thousands Yen/kWe. The power generation cost is estimated to be about 3.8Yen/kWh by the conditions of 90% load factor and 3% discount rate. The economical feasibility of the GTHTR300 is certified. The present study is entrusted from Ministry of Education, Culture, Sports, Science and Technology of Japan.
  • 片西 昌司, 武井 正信, 中田 哲夫, 國富 一彦
    日本原子力学会和文論文誌
    2004年 3 巻 1 号 67-75
    発行日: 2004/03/25
    公開日: 2010/03/08
    ジャーナル フリー
    日本原子力研究所(原研)では,2001年度から,高温ガス炉の熱利用研究の一環として,高温ガス炉を用いた電気出力300MW程度のガスタービン発電システム(Gas Turbine High Temperature Reactor 300: GTHTR300)の設計研究を行っている。これは,原研の高温ガス炉である高温工学試験研究炉(HTTR)における経験を踏まえて,高温ガス炉固有の安全上の特長を十分に活かした高い安全性をもつプラントシステムを構築し,かつ,十分な安全性を確保した上で安全機能の簡素化等をはかり経済性の点でも有利なプラントとすることを目指している。この設計研究の一環として,GTHTR300用燃料の設計とその成立性評価を行った。燃料の成立性評価としては,すでに報告したFP放出に対する障壁としての被覆燃料粒子の成立性評価に加え,燃料棒としての構造健全性について評価・検討した。
    GTHTR300の燃料設計に課される主な条件としては,HTTRに比べ出力密度が増加するため燃料から冷却材への効率的な伝熱をはかること,高燃焼度化に耐えられるものとすることおよび経済性を高めるために製作コストを抑えること等がある。これらの条件を満たすために,GTHTR300では,HTTRにおける燃料の開発経験をもとに,さらにそれを高性能化した燃料を使用することとした。すなわち,HTTRでは,円筒形の燃料コンパクトを黒鉛スリーブに収納して燃料棒としているのに対し,GTHTR300では,黒鉛スリーブは使用せず,燃料コンパクトを積み重ねたものを燃料棒とし,ヘリウムガスが直接燃料棒表面に接触して冷却する構造とした。また,GTHTR300における使用条件である高い燃焼度に対応できるものとするため,燃料粒子の被覆層を厚くすることとした。
    これまでに,FP放出に対する基本的障壁である被覆燃料粒子の被覆層の健全性について検討し,GTHTR300で予定している運転条件において,炉内滞在期間4年間で最大燃焼度約140GWd/tにおいても有意な破損はなく,被覆燃料粒子の健全性が保たれることを解析評価により確認し,平行して実施した経済性評価の結果と併せてすでに報告した。
    GTHTR300用燃料では,被覆燃料粒子を黒鉛とともに焼結した円筒形の燃料コンパクトを積み重ねた燃料棒を炉心に装荷する。この燃料棒について,通常運転中に予想される熱応力や地震による外力等に対して燃料棒としての健全性が保たれることも重要である。そこで,スリーブなしで燃料棒としての形状を保ち,かつ,応力や外力に対し十分な強度を持つようなGTHTR300独自の燃料棒の構造概念を考案し,地震等の荷重,通常運転時の熱膨張や照射変形,冷却材ヘリウムガスの圧力損失等に関して検討を行い,成立性のある燃料棒の具体的な構造を決定した。
    本報では,GTHTR300用高燃焼度燃料の成立性に関し,その第II報として,燃料棒の構造検討および構造健全性について検討した結果について報告する。
    本研究は,文部科学省から原研への委託により実施している電源特会「核熱利用システム技術開発」のうち「高温発電システム」として実施しているものである。
  • 片西 昌司, 京谷 正彦, 井上 公夫, 藤城 俊夫, 落合 政昭
    日本原子力学会誌
    1990年 32 巻 7 号 711-713
    発行日: 1990/07/30
    公開日: 2009/04/21
    ジャーナル フリー
  • 片西 昌司, 國富 一彦, 武井 正信, 中田 哲夫, 渡部 隆, 泉谷 徹
    日本原子力学会和文論文誌
    2002年 1 巻 4 号 373-383
    発行日: 2002/12/25
    公開日: 2010/01/21
    ジャーナル フリー
    Japan Atomic Energy Research Institute (JAERI) has been developing design studies of the Gas Turbine High Temperature Reactor (GTHTR300) based on the experiences of development of the High Temperature Engineering Test Reactor (HTTR) of JAERI. Feasibility of the GTHTR300 fuel which is irradiated under high burnup condition of approximately 140GWd/t at the maximum was investigated. It was certified that failure of coated fuel particles during irradiation will not occur and the integrity of coated fuel particles will be kept. Cost evaluation for fuel production and fuel cycle was also studied in order to clarify the economical feasibility which is important item for the development of the GTHTR300. The fuel cost per electricity production is estimated to be less than 1.1Yen/kWh. The feasibility of the fuel cost is certified.
    The present study is entrusted from Ministry of Education, Culture, Sports, Science and Technology of Japan.
  • 更田 豊治郎
    日本原子力学会誌
    2005年 47 巻 5 号 349
    発行日: 2005年
    公開日: 2019/01/31
    ジャーナル フリー
  • 西尾 雅七
    日本衛生学雑誌
    1946年 1 巻 1 号 2a-3
    発行日: 1946年
    公開日: 2010/08/10
    ジャーナル フリー
  • 國富 一彦, 片西 昌司, 高田 昌二, 小杉山 真一
    動力・エネルギー技術の最前線講演論文集 : シンポジウム
    2004年 2004.9 巻 NP3-05
    発行日: 2004/06/22
    公開日: 2017/06/19
    会議録・要旨集 認証あり
    The GTHTR300 (Gas Turbine High Temperature Reactor 300), which is expected to be deployed in 2010s as replacement for the LWR, is an economically competitive HTGR system to generate electricity by gas turbine. Basic principle of the safety design for the GTHTR300 was determined taking into account of inherent safety characteristics of the HTGR. Neither containment vessel nor emergency core cooling system is installed in the system. The elimination of these safety systems enhances economic advantage of the GTHTR300. The safety of the system was evaluated according to the newly established safety evaluation method. So far, the safety evaluation method has not determined for future commercial reactors such as the GTHTR300. It is of prime importance to determine the acceptance criteria to evaluate safety of the system. The paper mainly describes the acceptance criteria of the GTHTR300.
  • 片西 昌司, 國富 一彦, 辻 延昌, 前川 勇
    日本原子力学会和文論文誌
    2004年 3 巻 3 号 257-267
    発行日: 2004/09/25
    公開日: 2010/01/21
    ジャーナル フリー
    A design study program on the Gas Turbine High Temperature Reactor (GTHTR300) is being carried out in Japan Atomic Energy Research Institute (JAERI). Design of structures, systems and components which have fundamental engineering safety functions, such as shutdown of reactor, maintaining the coolability of reactor, prevention of the release of radioactivity, has progressed in this program. Coolability must be maintained even when a depressurization accident occurs which is the most severe event with loss of cooling function. The passive cooling system by using natural circulation of air was chosen because of simplicity of the system and its low cost. Cooling panels consisting of rectangular ducts were adopted after detail investigation on the capability of heat removal and on the structural integrity under high pressure condition during depressurization accident. This is an original design which is different from cooling panels in High Temperature Engineering Test Reactor (HTTR) of JAERI. Results of design study on performance of heat removal and structural integrity of passive cooling system of the GTHTR300 are described in this paper.
  • 斉藤 忠
    資源と素材
    1990年 106 巻 11 号 642-644
    発行日: 1990/10/25
    公開日: 2011/01/27
    ジャーナル フリー
  • 佐藤 博之, 大橋 弘史, 坂場 成昭, 西原 哲夫, 國富 一彦
    日本原子力学会和文論文誌
    2008年 7 巻 4 号 328-337
    発行日: 2008年
    公開日: 2012/03/02
    ジャーナル フリー
      One of the key technology requirements to achieve the non-nuclear-grade hydrogen plants coupled to the HTTR is the development of control methods mitigating the effect of IS process-abnormal thermal load transients on the reactor operation. This study focused on developing the control methods for the thermal mitigation system in the HTTR-IS system. The control methods are developed to stabilize the steam generator helium gas outlet temperature increase against the high-temperature helium gas inflow. The key parameters and equipment are determined and the control operations are simulated. The simulation results show that the steam generator water temperature can be effectively decreased by interfacing the actuation of the air cooler inlet shut-off valve with the actuation of the diverter valve. Furthermore, the air cooler outlet shut-off valve is activated as the pressure difference approaches zero between the steam generator bottom and the down comer from the air cooler to the steam generator. It is demonstrated that the control methods developed enable the continuation of the nuclear reactor normal operation under IS process abnormal conditions and without operator intervention.
  • 皆月 功, 溝上 頼賢
    日本原子力学会和文論文誌
    2007年 6 巻 3 号 276-288
    発行日: 2007年
    公開日: 2012/03/07
    ジャーナル フリー
      The design studies on High Temperature Gas Cooled Reactor with Gas Turbine (HTGR-GT) have been performed, which were mainly promoted by Japan Atomic Energy Agency (JAEA) and supported by fabricators in Japan. HTGR-GT plant feature is almost determined by selection of power conversion system concepts. Therefore, plant design philosophy is observed characteristically in selection of them.
      This paper describes the evaluation and analysis of the essential concepts of the HTGR-GT power conversion system through the investigations based on our experiences and engineering knowledge as a fabricator. As a result, the following concepts were evaluated that have advantages against other competitive one, such as the horizontal turbo machine rotor, the turbo machine in an individual vessel, the turbo machine with single shaft, the generator inside the power conversion vessel, and the power conversion system cycle with an intercooler. The results of the study can contribute as reference data when the concepts will be selected.
      Furthermore, we addressed reasonableness about the concept selection of the Gas Turbine High Temperature Reactor GTHTR300 power conversion system, which has been promoted by JAEA. As a conclusion, we recognized the GTHTR300 would be one of the most promising concepts for commercialization in near future.
  • 藤上 健太, 武田 哲明
    動力・エネルギー技術の最前線講演論文集 : シンポジウム
    2017年 2017.22 巻 A234
    発行日: 2017年
    公開日: 2017/12/25
    会議録・要旨集 認証あり

    A Very High Temperature Reactor (VHTR) is a next generation nuclear reactor system. From the view point of the safety characteristic, the passive cooling system should be designed for the VHTR as the best way of reactor vessel cooling system (VCS). Therefore, the gas cooling system with natural circulation is considered as a candidate for the VCS of the VHTR. Japan Atomic Energy Agency (JAEA) is advancing the technology development of the VHTR using the HTTR and is now pursuing design and development of commercial systems such as the 300MWe gas turbine high temperature reactor GTHTR300C (Gas Turbine High Temperature Reactor 300 for Cogeneration). The objective of this study is to investigate the heat transfer characteristics by natural convection in the vertical rectangular channel inserting the porous materials with high porosity. It is also to examine heat transfer characteristics of one side heated vertical rectangular channel with natural circulation in order to construct the passive cooling system of the VHTR. This paper describes the heat transfer coefficient and the amount of the removed heat in the proposed channel. In order to enhance the heat transfer, a porous material was inserted into the channel with high porosity. In order to apply to the VHTR such as GTHTR300C, it is necessary to perform a design study of the passive cooling system. This study is to refer to make design of the passive cooling system for the VCS.

  • 片西 昌司, 國富 一彦
    年次大会講演論文集
    2004年 2004.3 巻 2329
    発行日: 2004/09/04
    公開日: 2017/08/01
    会議録・要旨集 認証あり
    JAERI has undertaken the design study of gas turbine high temperature reactor, the GTHTR300. Design of fundamental safety functions, such as shutdown of rector, maintaining the coolability of reactor core and prevention of FP release has progressed in this design study program. Design of control rod arrangement and its insertion scheme was conducted in order to meet the safety requirement, such as a sufficient shutdown margin of reactivity and a low control rod ejection worth. A passive cooling system by using a natural convection of air was designed for maintaining the coolability during accident. Cooling panels consisting of rectangular ducts were adopted for sufficient capability of heat removal and structural integrity during depressurization accident. Double confinement was designed for mitigation of FP release and for maintaining the integrity of coated fuel particles and graphite material of fuel support structures. This article describes results of these design studies.
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