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Cryogenic hydrogen fuel for controlled inertial confinement fusion (formation of reactor-scale cryogenic targets)
Aleksandrova I.V., Koresheva E.R., Krokhin O.N., Osipov I.E.
Tokamak DEMO-FNS: Concept of magnet system and vacuum chamber
Azizov E.A., Kuteev B.V., Labusov A.N., Lukash V.E., Maximova I.I., Medvedev S.Y., Mineev A.B., Muratov V.P., Petrov V.S., Rodin I.Y., Sergeev V.Y., Spitsyn A.V., Tanchuk V.N., Trofimov V.A., Khayrutdinov R.R., Khokhlov M.V., Kuzmin E.G., Krylov V.A., Ananyev S.S., Belyakov V.A., Bondarchuk E.N., Voronova A.A., Golikov A.A., Goncharov P.R., Dnestrovskij A.Y., Zapretilina E.R., Ivanov D.P., Kavin A.A., Kedrov I.V., Klischenko A.V., Kolbasov B.N., Krasnov S.V., Krylov A.I., Shpanskiy Y.S.
Fusion and Space
Zhil’tsov V.A., Kulygin V.M.
Thermonuclear Power Engineering: 60 Years of Research. What Comes Next?
Strelkov V.S.
Influence of the Initial Defect Structure on Helium Trapping in Tungsten under Ion Implantation
Ryabtsev S.A., Gasparyan Y.M., Efimov V.S., Harutyunyan Z.R., Poskakalov A.G., Pisarev A.A., Kanashenko S.L., Ivanov Y.D.
Impact of Powerful Thermal and Neutron Fluxes on the Structural Elements of Fusion and Fission Reactors
Chirkov A.Y., Ryzhkov S.V.
Comparative analysis of the possibility of applying low-melting metals with the capillary-porous system in tokamak conditions
Lyublinski I.E., Vertkov A.V., Semenov V.V.
Emulation of Radiation Damage of Structural Materials for Fission and Fusion Power Plants Using Heavy Ion Beams
Useinov A.S., Rogozhkin S.V., Nikitin A.A., Khomich A.A., Iskandarov N.A., Khoroshilov V.V., Bogachev A.A., Lukyanchuk A.A., Raznitsyn O.A., Shutov A.S., Fedin P.A., Kuibeda R.P., Kulevoy T.V., Vasiliev A.L., Presniakov M.Y., Kravchuk K.S.
Radiation-Damaged Tungsten: Production and Study in a Steady-State Plasma Flux
Khripunov B.I., Stolyarova V.G., Semenov E.V., Muksunov A.M., Latushkin S.T., Kornienko S.N., Gureev V.M., Ryazanov A.I., Koidan V.S., Unezhev V.N.
Results of high heat flux tests of tungsten divertor targets under plasma heat loads expected in ITER and tokamaks (review)
Budaev V.P.
Multilevel System for Protecting the Cryogenic Target during Its Delivery to the Focus of High-Power Laser Facility at High Repetition Rate
Aleksandrova I.V., Koresheva E.R., Koshelev E.L.
Nuclear Power System Based on Fission and Fusion Reactors is the Strategic Line of Nuclear Power Industry Development
Velikhov E.P., Kovalchuk M.V., Ilgisonis V.I., Ignatiev V.V., Tsibulskiy V.F., Andrianova E.A., Blandinskiy V.Y.
On the History of the Development of Neutronics Codes for CTR Analysis at the Kurchatov Institute and the Validation of Neutron Data in Integral Experiments with 14-MeV Neutron Sources (Review)
Markovskij D.V.
Computer Simulation of Compression and Energy Release upon Laser Irradiation of Cylindrically Symmetric Target
Kuzenov V.V.
Hydrogen Retention in Tungsten Alloys Developed for Fusion Facilities (Review)
Golubeva A.V., Cherkez D.I.
Cryogenic Hydrogen Fuel for Controlled Inertial Confinement Fusion (Cryogenic Target Factory Concept Based on FST-Layering Method)
Aleksandrova I.V., Koresheva E.R., Koshelev I.E., Krokhin O.N., Nikitenko A.I., Osipov I.E.
Concept of Plasma Heating and Current Drive Neutral Beam System for Fusion Neutron Source DEMO-FNS
Ananyev S.S., Dlougach E.D., Krylov A.I., Kuteev B.V., Panasenkov A.A.
Advantages of Production of New Fissionable Nuclides for the Nuclear Power Industry in Hybrid Fusion-Fission Reactors
Tsibulskiy V.F., Andrianova E.A., Davidenko V.D., Rodionova E.V., Tsibulskiy S.V.
1 - 18 of 18 Items

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