ITER

Cadarash, France

ITER (""The Way"" in Latin) is one of the most ambitious energy projects in the world today.

ITERの研究史を読む公式サイト

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#核融合232#ITER189#トカマク92#ダイバータ57#プラズマ物理48#JET37#タングステン31#核融合炉25#EAST25#DIII-D20

装置分析

ジャーナル別論文数

FED

PPCF

POP

RSI

年別論文数推移

高精度マッチ高精度50件

The high heat flux components for ITER neutral beam system

E Di Pietro, T Inoue, A Panasenkov, A Krylov, V BykovFusion Engineering and Design2000

高精度タイトル一致

Detail design and manufacture of a prototype beryllium covered divertor baffle for ITER

A Erskine, K Cheyne, M Merola, J Turner, S KingFusion Engineering and Design2000

高精度タイトル一致

Fabrication of the wing and vertical target dummy armour prototypes of the ITER divertor

M Grattarola, M Bet, B Biagiotti, G Gandini, F ZacchiaFusion Engineering and Design2000

高精度

信頼度別論文数

高精度

3,700

低精度

794

中精度

1,390

Design issues and cost implications of RTO/RC-ITER divertor

C Ibbott, A Antipenkov, S Chiocchio, G Federici, R TiveyFusion Engineering and Design2000

高精度タイトル一致

Main achievements of the EU HT test programme of ITER primary wall small scale mock ups

P Lorenzetto, A Cardella, P Chappuis, W Daenner, S TähtinenFusion Engineering and Design2000

高精度タイトル一致

Design of a radiative semi-transparent liner for the ITER divertor cassette

A Makhankov, I Arkhipov, G Federici, A Gorodetsky, A ZakharovFusion Engineering and Design2000

高精度タイトル一致

Manufacturing of a full scale baffle prototype for ITER with a CFC and W plasma spray armour

M Merola, I Bobin-Vastra, A Cardella, M Febvre, G VieiderFusion Engineering and Design2000

高精度タイトル一致

Failure analysis of beryllium tile assemblies following high heat flux testing for the ITER program

B.C Odegard, C.H Cadden, N.Y.C Yang, R.D Watson, D.L YouchisonFusion Engineering and Design2000

高精度タイトル一致

Major achievements of the European shield blanket R&D during the ITER EDA, and their relevance for future next step machines

W Dänner, A Cardella, L Jones, P Lorenzetto, F TavassoliFusion Engineering and Design2000

高精度タイトル一致

FW/Blanket and vacuum vessel for RTO/RC ITER

K Ioki, V Barabash, A Cardella, F Elio, M YamadaFusion Engineering and Design2000

高精度タイトル一致

Improved modules for the blanket of RTO/RC ITER

F Elio, K Ioki, A CardellaFusion Engineering and Design2000

高精度タイトル一致

Neutronic shielding analysis of the water-cooled lithium lead test blanket module in the ITER machine

M RapisardaFusion Engineering and Design2000

高精度タイトル一致

Effect of ITER blanket manufacturing process on the properties of the 316L(N)-IG steel

B.S Rodchenkov, Y.S Strebkov, G.M Kalinin, O.A GolosovFusion Engineering and Design2000

高精度タイトル一致

Tritium inventory and permeation in the ITER breeding blanket

V. Violante, S. Tosti, C. Sibilia, F. Felli, C. AlvaniFusion Engineering and Design2000

高精度タイトル一致

Neutronic, thermal–hydraulic and stress analysis of RF lithium cooled test blanket module for ITER

I.V Vitkovsky, M.M Golovanov, V.A Divavin, I.R Kirillov, O.L SchipakinFusion Engineering and Design2000

高精度タイトル一致

Tritium recovery from an ITER ceramic test blanket module — process options and critical R&D issues

H. Albrecht, E. HutterFusion Engineering and Design2000

高精度タイトル一致

A design study of water detritation and hydrogen isotope separation systems for ITER

Y. Iwai, H. Yoshida, T. Yamanishi, S. Senrui, M. NishiFusion Engineering and Design2000

高精度タイトル一致

Fuel cycle design evolution from FDR-ITER to RTO/RC-ITER

D.K Murdoch, M Glugla, O KvetonFusion Engineering and Design2000

高精度タイトル一致

Catalytic membrane reactors for tritium recovery from tritiated water in the ITER fuel cycle

S Tosti, V Violante, A Basile, G Chiappetta, F SartoFusion Engineering and Design2000

高精度タイトル一致

The influence of water on the performance of ITER cryosorption vacuum pumps

Chr Day, B Kammerer, A MackFusion Engineering and Design2000

高精度タイトル一致

Design of the RTO/RC ITER primary pumping system

P Ladd, C Ibbott, G Janeschitz, E MartinFusion Engineering and Design2000

高精度タイトル一致

Design and analysis of the vacuum vessel for RTO/RC-ITER

M Onozuka, K Ioki, G Johnson, T Kodama, Y UtinFusion Engineering and Design2000

高精度タイトル一致

Nuclear performance of the D–D phase of ITER

V. KhripunovFusion Engineering and Design2000

高精度タイトル一致

Neutronics analysis of the ITER NB system: Nuclear responses of the components and shutdown dose around the NB injector

K Shibata, K Maki, T Inoue, M Hanada, Y YamashitaFusion Engineering and Design2000

高精度タイトル一致

Nuclear aspects of diagnostics in RTO/RC ITER

C.I. Walker, S. Yamamoto, A. Costley, L. deKock, G. VayakisFusion Engineering and Design2000

高精度タイトル一致

Safety design for ITER and fusion power reactors

H.-W. BartelsFusion Engineering and Design2000

高精度タイトル一致

Possibilities for disposal of ITER waste in three European countries

Karin Brodén, Maria Lindberg, Gunnar OlssonFusion Engineering and Design2000

高精度タイトル一致

Dust and corrosion product effluents assessment in ITER

G Cambi, D.G Cepraga, L Di Pace, C Rizzello, M ZucchettiFusion Engineering and Design2000

高精度タイトル一致

Application of SEAFP waste recycling and clearance strategies to ITER

E.T Cheng, P Rocco, M ZucchettiFusion Engineering and Design2000

高精度タイトル一致

Application of the safety method of the lines of defence for two ITER accidents

M Costa, G.L FioriniFusion Engineering and Design2000

高精度タイトル一致

Numerical study on pressure rise characteristics in simulated ITER structural components during ingress-of-coolant events

K. Takase, Y. Ose, H. AkimotoFusion Engineering and Design2000

高精度タイトル一致

Lithium safety in fusion systems (ITER)

T.T Utschig, M.L CorradiniFusion Engineering and Design2000

高精度タイトル一致

ITER relevant ICRF heating scenarios with large ion heating fraction

V. Bergeaud, L.-G. Eriksson, D.F.H. StartNuclear Fusion2000被引用: 23

高精度タイトル一致

ITER Physics Basis Chapter 5: Physics of energetic ions

ITER Physics Expert Group on Energetic Particles, Heating and Current Drive, ITER Physics Basis EditorsNuclear Fusion2000被引用: 1

高精度タイトル一致

ITER in-vessel system design and performance

R.R. ParkerNuclear Fusion2000被引用: 20

高精度タイトル一致

Operation and control of ITER plasmas

J. Wesley, H.-W. Bartels, D. Boucher, A.E. Costley, L. DeKock, S. Gerasimov, Yu. Gribov, G. Janeschitz, L. Johnson, P.L. MondinoNuclear Fusion2000被引用: 7

高精度タイトル一致

ITER plant layout and site services

V.A. ChuyanovNuclear Fusion2000被引用: 3

高精度タイトル一致

ITER neutral beam system

P.L. Mondino, P. Bayetti, E. Di Pietro, R.S. Hemsworth, H. Iida, T. Inoue, K. Ioki, G. Johnson, A.I. Krylov, V.M. KulyginNuclear Fusion2000被引用: 27

高精度タイトル一致

The development of a negative ion beam plasma neutralizer for ITER NBI

V.A. Zhil'tsov, E.Yu. Klimenko, P.M. Kosarev, V.M. Kulygin, V.V. Platonov, N.N. Semashko, A.A. Skovoroda, V.P. Ukhov, A.A. Mehed'kinNuclear Fusion2000被引用: 19

高精度タイトル一致

Development of a tritium fuel processing system using an electrolytic reactor for ITER

T. Yamanishi, Y. Kawamura, Y. Iwai, T. Arita, T. Maruyama, T. Kakuta, S. Konishi, M. Enoeda, S. Ohira, T. HayashiNuclear Fusion2000被引用: 7

高精度タイトル一致

Improvement of tritium accountancy technology for ITER fuel cycle safety enhancement

S. O'hira, T. Hayashi, H. Nakamura, K. Kobayashi, T. Tadokoro, H. Nakamura, T. Itoh, T. Yamanishi, Y. Kawamura, Y. IwaiNuclear Fusion2000被引用: 26

高精度タイトル一致

European contributions to the beam source design and R&D of the ITER neutral beam injectors

P. Massmann, P. Bayetti, J. Bucalossi, C. Desgranges, E. Di Pietro, P. Frank, M. Fumelli, Y. Fujiwara, M. Hanada, B. HeinemannNuclear Fusion2000被引用: 11

高精度タイトル一致

ITER Physics Basis Chapter 6: Plasma auxiliary heating and current drive

ITER Physics Expert Group on Energetic Particles, Heating and Current Drive, ITER Physics Basis EditorsNuclear Fusion2000被引用: 3

高精度タイトル一致

Transport simulation of ITER scenarios with driven burn

G. BeckerNuclear Fusion2000被引用: 2

高精度タイトル一致

Physics and goals of RTO/RC-ITER

D J CampbellPlasma Physics and Controlled Fusion1999

高精度タイトル一致

Physics fundamentals for ITER

M N RosenbluthPlasma Physics and Controlled Fusion1999