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High temperature gas-cooled reactors (JSME series in thermal and nuclear power generation ; volume 5)

High temperature gas-cooled reactors (JSME series in thermal and nuclear power generation ; volume 5)
紙図書
edited by Tetsuaki Takeda, Yoshiyuki InagakiElsevier[2021]<NG41-D2>
国立国会図書館全国の図書館
  • 件名Gas cooled reactors--Design and construction Gas cooled reactors--Safety measures Gas cooled reactors--Design and construction. Gas cooled reactors--Safety measures.

International congress on advances in nuclear power plants (ICAPP 2018) : Charlotte, North Carolina, USA : 8-11 April 2018 : Apr 2018, Charlotte, NC.

International congress on advances in nuclear power plants (ICAPP 2018) : Charlotte, North Carolina, USA : 8-11 April 2018 : Apr 2018, Charlotte, NC.
紙図書
American Nuclear Society[2018]<M17-19-1407>
国立国会図書館
  • 件名...type reactors. Gas cooled reactors. Fast reactors. PWR type reac...

High temperature gas cooled reactor fuels and materials (IAEA-TECDOC-CD ; 1645)

High temperature gas cooled reactor fuels and materials (IAEA-TECDOC-CD ; 1645)
記録メディア電子資料
International Atomic Energy Agency2010.<YH245-B1112>
国立国会図書館
  • 要約等...gh temperature gas cooled reactors (HTGRs) with an aim to build ...
  • 件名Gas cooled reactors. Nuclear fuels. Nuclear react...

Accident analysis for nuclear power plants with modular high temperature gas cooled reactors / International Atomic Energy Agency. (Safety reports series ; no. 54)

Accident analysis for nuclear power plants with modular high temperature gas cooled reactors / International Atomic Energy Agency. (Safety reports series ; no. 54)
紙図書
International Atomic Energy Agency2008.<A163-B817>
国立国会図書館
  • 要約等...gh temperature gas cooled reactors (HTGRs) . It contains details...
  • 件名...fety measures. Gas cooled reactors.

Materials behavior in HTGR environments [microform] / prepared by K. Natesan, A. Purohit, S.W. Tam NUREG/CR-6824 ANL-02/37

Materials behavior in HTGR environments [microform] / prepared by K. Natesan, A. Purohit, S.W. Tam NUREG/CR-6824 ANL-02/37
マイクロ図書
2003<YCA-Y 3.N 88:25/6824>
国立国会図書館
  • 件名Gas cooled reactors Nuclear reactors -- Materials...

Basic studies in the field of high-temperature engineering : third information exchange meeting, Ibaraki-ken, Japan, 11-12 September 2003 : co-organized by the Japan Atomic Energy Research Institute (JAERI). (Nuclear science)

Basic studies in the field of high-temperature engineering : third information exchange meeting, Ibaraki-ken, Japan, 11-12 September 2003 : co-organized by the Japan Atomic Energy Research Institute (JAERI). (Nuclear science)
紙図書
Nuclear Energy Agency, Organisation for Economic Co-operation and Developmentc2004.<DE64-B1781>
国立国会図書館全国の図書館
  • 件名Gas cooled reactors -- Congresses. Heat resistant...

Basic studies in the field of high-temperature engineering : second information exchange meeting, Paris, France, 10-12 October 2001 / co-organized by the Japan Atomic Energy Research Institute. (Nuclear science)

Basic studies in the field of high-temperature engineering : second information exchange meeting, Paris, France, 10-12 October 2001 / co-organized by the Japan Atomic Energy Research Institute. (Nuclear science)
紙図書
Nuclear Energy Agency, Organisation for Economic Co-operation and Developmentc2002.<NG41-B13>
国立国会図書館全国の図書館
  • 件名Gas cooled reactors -- Congresses. Heat resistant...

Magnitude and reactivity consequences of moisture ingress into the modular high-temperature gas-cooled reactor core microform / prepared by O.L. Smith

Magnitude and reactivity consequences of moisture ingress into the modular high-temperature gas-cooled reactor core microform / prepared by O.L. Smith
マイクロ図書
1992<YCA-Y 3.N 88:25/5947>
国立国会図書館
  • 件名Gas cooled reactors -- Moisture Gas cooled reactors -- Safety measures

ヘリウムガス冷却炉プラント動特性解析評価 : 研究報告 (JNC TN9400 ; 2003-100)

ヘリウムガス冷却炉プラント動特性解析評価 : 研究報告 (JNC TN9400 ; 2003-100)
紙図書
核燃料サイクル開発機構大洗工学センター2003.8<NG41-H248>
国立国会図書館
  • 典拠情報（件名/「を見よ」参照）GCR Gas cooled reactors

Evaluation of MHTGR fuel reliability [microform] / prepared by R.P. Wichner, W.P. Barthold

Evaluation of MHTGR fuel reliability [microform] / prepared by R.P. Wichner, W.P. Barthold
マイクロ図書
1992<YCA-Y 3.N 88:25/5810>
国立国会図書館
  • 件名Gas cooled reactors Nuclear fuels

Fission product plateout and liftoff in the MHTGR primary system : a review / prepared by R.P. Wichner

Fission product plateout and liftoff in the MHTGR primary system : a review / prepared by R.P. Wichner
マイクロ図書
1991<YCA-Y 3.N 88:25/5647>
国立国会図書館
  • 件名Gas cooled reactors Fission products

ガス冷却炉の検討 (JNC TN9400 ; 2000-73)

ガス冷却炉の検討 (JNC TN9400 ; 2000-73)
紙図書
核燃料サイクル開発機構大洗工学センター2000.6<NG41-G323>
国立国会図書館
  • 典拠情報（件名/「を見よ」参照）GCR Gas cooled reactors

MORECA-2 microform : interactive simulator for modular high-temperature gas-cooled reactor core transients and heatup accidents with ATWS options / prepared by S.J. Ball, D.J. Nypaver

MORECA-2 microform : interactive simulator for modular high-temperature gas-cooled reactor core transients and heatup accidents with ATWS options / prepared by S.J. Ball, D.J. Nypaver
マイクロ図書
1992<YCA-Y 3.N 88:25/5945>
国立国会図書館
  • 件名Gas cooled reactors -- Accidents -- Computer simu...

炭酸ガス冷却炉におけるオーステナイト系炉心材料の腐食に関する調査・検討 : 研究報告 (JNC TN9400 ; 2000-32)

炭酸ガス冷却炉におけるオーステナイト系炉心材料の腐食に関する調査・検討 : 研究報告 (JNC TN9400 ; 2000-32)
紙図書
核燃料サイクル開発機構大洗工学センター2000.3<NG61-G57>
国立国会図書館
  • 典拠情報（件名/「を見よ」参照）Nuclear reactors--Materials GCR Gas cooled reactors

炭酸ガス冷却炉におけるフェライト系炉心材料の腐食に関する調査・検討 : 研究報告 (JNC TN9400 ; 2000-40)

炭酸ガス冷却炉におけるフェライト系炉心材料の腐食に関する調査・検討 : 研究報告 (JNC TN9400 ; 2000-40)
紙図書
核燃料サイクル開発機構大洗工学センター2000.3<NG61-G53>
国立国会図書館
  • 典拠情報（件名/「を見よ」参照）Nuclear reactors--Materials GCR Gas cooled reactors

ヘリウムガス冷却炉被覆粒子燃料層内における詳細熱流動解析 : 研究報告 (JNC TN9400 ; 2001-101)

ヘリウムガス冷却炉被覆粒子燃料層内における詳細熱流動解析 : 研究報告 (JNC TN9400 ; 2001-101)
紙図書
核燃料サイクル開発機構大洗工学センター2001.6<NG61-G138>
国立国会図書館
  • 典拠情報（件名/「を見よ」参照）原子炉--冷却材 GCR Gas cooled reactors

Accident analysis for nuclear power plants with modular high temperature gas cooled reactors : pbk

Accident analysis for nuclear power plants with modular high temperature gas cooled reactors : pbk
紙図書
International Atomic Energy AgencyInternational Atomic Energy Agency2008
全国の図書館
  • 件名...afety measures Gas cooled reactors
  • 件名（識別子）...afety measures Gas cooled reactors
  • 一般注記...gh temperature gas cooled reactors (HTGRs). It contains details ...

Modeling and performance of the MHTGR reactor cavity cooling system [microform] / prepared by J.C. Conklin

Modeling and performance of the MHTGR reactor cavity cooling system [microform] / prepared by J.C. Conklin
マイクロ図書
1990<YCA-Y 3.N 88:25/5514>
国立国会図書館
  • 件名Gas cooled reactors -- Cooling -- Mathematical mo...

Safety aspects of forced flow cooldown transients in modular high temperature gas-cooled reactors microform / prepared by P.G. Kroger

Safety aspects of forced flow cooldown transients in modular high temperature gas-cooled reactors microform / prepared by P.G. Kroger
マイクロ図書
1993<YCA-Y 3.N 88:25/5983>
国立国会図書館
  • 件名Gas cooled reactors -- Cooling -- Safety measures...

Modelling and measuring reactor core graphite properties and performance hbk.

Modelling and measuring reactor core graphite properties and performance hbk.
紙図書
editor, Gareth B. NeighbourRoyal Society of Chemistryc2013
全国の図書館
  • 件名Gas cooled reactors -- Safety measures Graphite -...
  • 件名（識別子）Gas cooled reactors -- Safety measures Graphite -...