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ITER, the giant fusion reactor : bringing a sun to earth Second edition (Copernicus books)

ITER, the giant fusion reactor : bringing a sun to earth Second edition (Copernicus books)
紙図書
Michel ClaessensSpringer[2023]<NG41-D25>
国立国会図書館全国の図書館

Plasma-material interactions in a controlled fusion reactor (Springer series in plasma science and technology)

Plasma-material interactions in a controlled fusion reactor (Springer series in plasma science and technology)
紙図書
Tetsuo TanabeSpringer[2021]<MC241-D3>
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Tritum technologies for thermonuclear fusion reactors

Tritum technologies for thermonuclear fusion reactors
紙図書
Alexander Perevezentsev, Mikhail RozenkevichAcademic Press[2021]<NG41-D9>
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Fusion reactor design : plasma physics, fuel cycle system, operation and maintenance

Fusion reactor design : plasma physics, fuel cycle system, operation and maintenance
紙図書
Takashi OkazakiWiley-VCH[2022]<NG41-D15>
国立国会図書館全国の図書館

Time-dependent calorimetric analysis for estimation and control of heat load to plasma facing components in future fusion reactors

Time-dependent calorimetric analysis for estimation and control of heat load to plasma facing components in future fusion reactors
デジタル博士論文障害者向け資料あり
Bui, Xuan Nhat Son2023-09-23
インターネットで読める国立国会図書館全国の図書館

STUDY FOR THE EXPERIMENTAL ANALYSIS OF NEUTRON TRANSPORT AND TRITIUM BREEDING PERFORMANCE INSIDE FUSION REACTOR BLANKET

STUDY FOR THE EXPERIMENTAL ANALYSIS OF NEUTRON TRANSPORT AND TRITIUM BREEDING PERFORMANCE INSIDE FUSION REACTOR BLANKET
デジタル博士論文障害者向け資料あり
Ogino, Yasuyuki2022-03-23
インターネットで読める国立国会図書館全国の図書館

Study on the ceramic materials for solid type breeding blanket in fusion reactor

Study on the ceramic materials for solid type breeding blanket in fusion reactor
デジタル博士論文障害者向け資料あり
金, 鍾壹2021-03-23
インターネットで読める国立国会図書館全国の図書館

The effect of point defects on irradiation damage of Fe-based composite materials for fusion reactor

The effect of point defects on irradiation damage of Fe-based composite materials for fusion reactor
デジタル博士論文障害者向け資料あり
史, 鏡明Hokkaido University2020-09-25
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Ultra-Small Testing Technologies for Predicting Macroscopic Strength of Oxide Dispersion Strengthened Copper Alloy as a Potential Heat Sink Material in Fusion Reactor Divertor

Ultra-Small Testing Technologies for Predicting Macroscopic Strength of Oxide Dispersion Strengthened Copper Alloy as a Potential Heat Sink Material in Fusion Reactor Divertor
デジタル博士論文障害者向け資料あり
LIU, YUCHEN2021-03-25
国立国会図書館

Ultra-small testing technologies for predicting macroscopic strength of oxide dispersion strengthened copper alloy as a potential heat sink material in fusion reactor divertor

Ultra-small testing technologies for predicting macroscopic strength of oxide dispersion strengthened copper alloy as a potential heat sink material in fusion reactor divertor
紙博士論文
Yuchen Liu [著][2021]<UT51-2021-A868>
国立国会図書館

Tritium: fuel of fusion reactors

Tritium: fuel of fusion reactors
紙図書
Tetsuo Tanabe editorSpringerc2017<NG71-B35>
国立国会図書館

Study on the transport of high heat flux and the thermal mechanical response in fusion reactor divertor

Study on the transport of high heat flux and the thermal mechanical response in fusion reactor divertor
デジタル博士論文障害者向け資料あり
権, 暁星権, 暁星2014
国立国会図書館

Study on tritium production property by D-T and D-D neutrons of LiPb blanket for fusion reactor

Study on tritium production property by D-T and D-D neutrons of LiPb blanket for fusion reactor
デジタル博士論文障害者向け資料あり
Kwon, Saerom2014-03-24
インターネットで読める国立国会図書館全国の図書館

Study on hydrogen isotopes behavior in liquid breeder materials of fusion reactor

Study on hydrogen isotopes behavior in liquid breeder materials of fusion reactor
紙博士論文
Yuki Edao [著][Yuki Edao][2012]<UT51-2012-D450>
国立国会図書館

Studies on electrochemical surface modification for molten-salt blanket system in fusion reactor

Studies on electrochemical surface modification for molten-salt blanket system in fusion reactor
紙博士論文
Takashi Watanabe [著][Takashi Watanabe][2012]<UT51-2012-J670>
国立国会図書館

Design study of small power tokamak nuclear fusion reactor for the biomass-fusion hybrid concept

Design study of small power tokamak nuclear fusion reactor for the biomass-fusion hybrid concept
紙博士論文
Kenzo Ibano [著][Kenzo Ibano][2012]<UT51-2012-L637>
国立国会図書館

Neutronics studies on advanced blankets for tokamak fusion reactors

Neutronics studies on advanced blankets for tokamak fusion reactors
紙博士論文
Takao Hayashi [著][Takao Hayashi][2010]<UT51-2010-C604>
国立国会図書館

Design of multi functional vacuum vessel for fusion reactor

Design of multi functional vacuum vessel for fusion reactor
紙博士論文
Masaaki Morimoto [著][Masaaki Morimoto][2008]<UT51-2008-J391>
国立国会図書館

Design study on fast-ignition laser fusion reactor with a dry wall chamber

Design study on fast-ignition laser fusion reactor with a dry wall chamber
紙博士論文
後藤拓也 [著][後藤拓也][2008]<UT51-2008-S520>
国立国会図書館

Study on tritium release behavior from solid breeder materials of D-T fusion reactor

Study on tritium release behavior from solid breeder materials of D-T fusion reactor
紙博士論文
Tomohiro Kinjyo [著][Tomohiro Kinjyo][2007]<UT51-2007-S879>
国立国会図書館