Fusion Engineering and Designжурнал

Статьи, опубликованные в журнале

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  • 2023 Radiation control in Tritium and Deuterium-Tritium JET baseline plasmas – part II
  • Piron L., Van Eester D., Frigione D., Garzotti L., Lomas P.J., Lennholm M., Rimini F., Auriemma F., Baruzzo M., Carvalho P.J., Ferreira D.R., Field A.R., Kirov K., Stancar Z., Stuart C.I., Valcarcel D., Suchkov E., JET Contributors
  • в журнале Fusion Engineering and Design, издательство Elsevier BV (Netherlands), том 192 DOI
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  • 2023 Radiation control in deuterium, tritium and deuterium-tritium JET baseline plasmas – part I
  • Piron L., Van Eester D., Frigione D., Garzotti L., Lomas P.J., Lennholm M., Rimini F., Auriemma F., Baruzzo M., Carvalho P.J., Ferreira D.R., Field A.R., Kirov K., Stancar Z., Stuart C.I., Valcarcel D., Suchkov E., JET Contributors
  • в журнале Fusion Engineering and Design, издательство Elsevier BV (Netherlands), том 193 DOI
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  • 2023 Retention of noble and rare isotope gases in plasma-facing components – Experience from the JET tokamak with the ITER-like wall
  • Dittrich Laura, Petersson Per, Moon Sunwoo, Rubel Marek, Tran Tuan Thien, Widdowson Anna, Suchkov E., JET Contributors
  • в журнале Fusion Engineering and Design, издательство Elsevier BV (Netherlands), том 192 DOI
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  • 2022 New horizontal and vertical field coils with optimised location for robust decentralized plasma position control in the IGNITOR tokamak
  • Mitrishkin Y.V., Korenev P.S., Konkov A.E., Kartsev N.M., Smirnov I.S.
  • в журнале Fusion Engineering and Design, издательство Elsevier BV (Netherlands), том 174, с. 1-20 DOI
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  • 2021 Post-mortem analyses of gap facing surfaces of tungsten tiles of T-10 ring limiter
  • Pisarev A., Arkhipov I., Babich Ya, Berdnikiva M., Gasparyan Yu, Gutorov K., Grashin S., Efimov V., Isaenkova M., Krat S., Krymskaya О., Kurnaev V., Stepanova Т., Vovchenko E., Visgalov I., Zibrov M.
  • в журнале Fusion Engineering and Design, издательство Elsevier BV (Netherlands), том 162 DOI
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  • 2021 Tritium retention in displacement-damaged tungsten exposed to deuterium-tritium gas mixture at elevated temperatures
  • Alimov V.Kh, Torikai Y., Hatano Y., Schwarz-Selinger T.
  • в журнале Fusion Engineering and Design, издательство Elsevier BV (Netherlands), том 162, с. 112100-6pp DOI
• • 2020 Thermal conductivity and thermal diffusivity of Li-Pb eutectic in the temperature range of 293–1273 K
  • Agazhanov A.Sh, Abdullaev R.N., Samoshkin D.A., Stankus S.V.
  • в журнале Fusion Engineering and Design, издательство Elsevier BV (Netherlands), том 152 DOI
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  • 2019 Analysis of mixed-material layers deposited on the toroidal array probes during the FY 2012 LHD plasma campaign
  • Alimov V.Kh, Yajima M., Masuzaki S., Tokitani M.
  • в журнале Fusion Engineering and Design, издательство Elsevier BV (Netherlands), том 147, с. 111228 DOI
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  • 2019 Current inverter as self-oscillating actuator in applications for plasma position control systems in the Globus-M/M2 and T-11M tokamaks
  • Kuznetsov Evgeniy A., Mitrishkina Yuri V., Kartsev Nikolay M.
  • в журнале Fusion Engineering and Design, издательство Elsevier BV (Netherlands), том 143, с. 247-258
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  • 2019 Hierarchical robust switching control method with the equilibrium reconstruction code based on improved Moving Filaments approach in the feedback for tokamak plasma shape
  • Mitrishkin Y.V., Prokhorov A.A., Korenev P.S., Patrov M.I.
  • в журнале Fusion Engineering and Design, издательство Elsevier BV (Netherlands), том 138, с. 138-150
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  • 2019 ITER-grade tungsten limiters damage under high turbulent heat flux in the T-10 tokamak
  • Grashin S.A., Arkhipov I.I., Budaev V.P., Karpov A.V., Klyuchnikov L.A., Khimchenko L.N., Melnikov A.V., Sarychev D.V., Sergeev N.S., Zemtsov I.A.
  • в журнале Fusion Engineering and Design, издательство Elsevier BV (Netherlands), том 146, № Part В, с. 2100-2104 DOI
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  • 2019 Refinement of thermonuclear reaction rates
  • Belov A.A., Kalitkin N.N., Kozlitin I.A.
  • в журнале Fusion Engineering and Design, издательство Elsevier BV (Netherlands), том 141, с. 51-58 DOI
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  • 2019 Scope of modification of the TRINITI site fuel cycle complex for the IGNITOR project tasks: System of isotopes storage
  • Rozenkevich M.B., Perevezentsev A.N., Subbotin M.L., Gostev A.A.
  • в журнале Fusion Engineering and Design, издательство Elsevier BV (Netherlands), том 146, с. 924-927
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  • 2016 Continuous, saturation, and discontinuous tokamak plasma vertical position control systems
  • Mitrishkin Y.V., Pavlova E.A., Kuznetsov E.A., Gaydamaka K.I.
  • в журнале Fusion Engineering and Design, издательство Elsevier BV (Netherlands), том 108, с. 35-47 DOI
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  • 2016 Influence of displacement damages on deuterium retention in reduced activation ferritic/martensitic steels F82H and Eurofer97
  • Alimov Vladimir Kh, Hatano Yuji, Sugiyama Kazuyoshi, Kondo Sosuke, Hinoki Tatsuya, Tokitani Masayuki
  • в журнале Fusion Engineering and Design, издательство Elsevier BV (Netherlands), том 113, с. 336-339
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  • 2016 Numerical modeling and design of a disk-type rotating permanent magnet induction pump
  • Koroteeva E., Ščepanskis M., Bucenieks I., Platacis E.
  • в журнале Fusion Engineering and Design, издательство Elsevier BV (Netherlands), том 106, с. 85-92 DOI
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  • 2016 Recent progress of hydrogen isotope behavior studies for neutron or heavy ion damaged W
  • Oya Yasuhisa, Hatano Yuji, Shimada Masashi, Buchenauer Dean, Kolasinski Robert, Merrill Brad, Kondo Sosuke, Hinoki Tatsuya, Alimov Vladimir Kh
  • в журнале Fusion Engineering and Design, издательство Elsevier BV (Netherlands), том 113, с. 211-215 DOI
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  • 2015 Physical Program and Diagnostics of the T-15 Upgrade Tokamak: Brief Overview
  • Melnikov A.V., Sushkov A.V., Belov A.M., Dnestrovskij Yu N., Eliseev L.G., Ivanov D.P., Kirneva N.A., Korobov K.V., Krupin V.A., Lysenko S.E., Mukhovatov V.S., Mustafin N.A., Perfilov S.V., Razumova K.A., Roy I.N., Savrukhin P.V., Strelkov V.S., Shestakov E.A., Tilinin and V L Vdovin G.N.
  • в журнале Fusion Engineering and Design, издательство Elsevier BV (Netherlands), том 96, с. 306-310
• • 2009 Computational modelling of the IFMIF lithium target
  • Titarev V.A., Romenski E., Drikakis D., Surrey E.
  • в журнале Fusion Engineering and Design, издательство Elsevier BV (Netherlands), том 84, № 1, с. 49-56 DOI
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  • 2008 Conceptual design of a component test facility based on the spherical tokamak
  • Voss G.M., Davis S., Dnestrovskij A., Kirk A., Knight P.J., Loughlin M., O’Brien M.H., Sychugov D., Tabasso A., Wilson H.R.
  • в журнале Fusion Engineering and Design, издательство Elsevier BV (Netherlands), том 83, с. 1648-1653
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  • 2008 Conceptual design of a component test facility based on the spherical tokamak
  • Voss G.M., Davis S., Dnestrovskij A., Kirk A., Knight P.J., Loughlin M., O’Brien M.H., Sychugov D., Tabasso A., Wilson H.R.
  • в журнале Fusion Engineering and Design, издательство Elsevier BV (Netherlands), том 83, с. 1648-1653
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  • 2007 Radiation assessment of hydrogen-loaded aluminium-coated pure silica core fibres for ITER plasma diagnostic applications
  • Brichard B., Tomashuk A.L., Ooms H., Bogatyrjov V.A., Klyamkin S.N., Fernandez A.F., Berghmans F., Decreton M.
  • в журнале Fusion Engineering and Design, издательство Elsevier BV (Netherlands), том 82, № 15-24, с. 2451-2455 DOI
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  • 2004 The development of low aspect ratio tokamaks in Russia
  • Azizov E.A., Buzhinskij O.I., Velikhov E.P., Gladush G.G., Kovan I.A., Mineev A.B., Khayrutdinov R.R., Obysov N.A.
  • в журнале Fusion Engineering and Design, издательство Elsevier BV (Netherlands), том 70, № 1, с. 45-56 DOI
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  • 2003 Accumulation of deuterium in sputtered and re-deposited layers of Be and W under their simultaneous irradiation by deuterons
  • Danelyan L.S., Elistratov N.G., Gureev V.M., Guseva M.I., Kolbasov B.N., Kulikauskas V.S., Vasihev N.N., Zatekin V.V., Zimin A.M.
  • в журнале Fusion Engineering and Design, издательство Elsevier BV (Netherlands), том 66, с. 431-435
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  • 2001 Fusion power plant for water desalination and reuse
  • Borisov A.A., Desjatov A.V., Izvolsky I.M., Serikov A.G., Smirnov V.P., Smirnov Y.N., Shatalov G.E., Sheludjakov S.V., Vasiliev N.N., Velikhov E.P.
  • в журнале Fusion Engineering and Design, издательство Elsevier BV (Netherlands), том 58, с. 1109-1115 DOI