Results 161 to 170 of about 8,080 (185)

Materials selection and design for the International Thermonuclear Experimental Reactor(ITER)

Journal of Fusion Energy, 1992
The International Thermonuclear Experimental Reactor (ITER) program is a multinational effort to design and develop the technology for a superconducting magnetic fusion energy reactor that can achieve long burn times using a deuterium-tritium fuel. During the recently completed Conceptual Design Activity (CDA), teams from the U.S., Japan, Soviet Union,
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The absorption of deuterium by carbon-based facing materials on components in contact with the plasma in a thermonuclear reactor

Atomic Energy, 1997
The conditions have been proposed for performing modeling experiments making it possible to predict the accumulation of hydrogen isotopes in carbon materials which are in contact with a tokamak plasma acting as a source of particles having a flux density of between 3×1016 and 3×1019 cm−2·sec−1.
A. E. Gorodetskii, A. V. Markin, V. N. Chernikov, A. P. Zakharov, T. A. Burtseva, I. V. Mazul, N. N. Shipkov, G. D. Tolstolutskaya, V. F. Rybalko   +8 more
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Suppression of the radiation hardening and embrittlement of International Thermonuclear Experimental Reactor materials by multiple intermediate annealing

Plasma Devices and Operations, 2008
The paper presents the results from an experimental study on the effect of neutron irradiation in the ‘irradiation–annealing–irradiation (IAI)’ regime on the radiation hardening and embrittlement of pure copper. An ampoule with samples was irradiated at T in=150 °C in the RBT-6 reactor in the following regime: ‘irradiation to 0.004 dpa+annealing at 250 
S. A. Fabritsiev, A. S. Pokrovsky
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Deuterium Plasma Focus as a Tool for Testing Materials of Plasma Facing Walls in Thermonuclear Fusion Reactors

Journal of Fusion Energy, 2016
This paper presents the first verification of the fast ion beam (FIB) and fast plasma stream (FPS) properties computed using the Lee code. Recent estimates of FIB and FPS properties in PF-400J from interferometric images are compared to our computed results. Reasonable agreement is found in the comparison of several quantities.
Akel, M., Alsheikh Salo, S., Ismael, S., Saw, S.H., Lee, S.   +4 more
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Mechanical properties of oxygen-injected vanadium alloy for application as structural component material for international thermonuclear experimental reactor

Journal of Nuclear Materials, 1996
Abstract The effect of oxygen injection on the mechanical properties of vanadium alloys was investigated. Tensile testing of oxygen-containing and reference specimens were performed at temperatures up to 1000°C. Results show that, in general, oxygen decreases the ductility and increases the ultimate tensile stress.
O.A. Medvedev, A.I. Ryazanov, A.N. Lyubimov, Y.V. Tichonov, W. van Witzenburg   +4 more
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Problem Areas in the First-Wall Materials of a Controlled Thermonuclear Reactor

1974
There are at present several design schemes for controlled thermonuclear reactors (CTR) which involve magnetic containment of a D-T reaction. In these designs thermal energy will be extracted through a heat-transfer wall to a coolant which is coupled to a steam power conversion system.
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An Intense Li(d,n) Neutron Radiation Test Facility for Controlled Thermonuclear Reactor Materials Testing

Nuclear Technology, 1976
Brookhaven National Laboratory has proposed the construction of an intense Li(d,n) neutron source. The neutron production process is based on the stripping reaction of energetic deuterons on a flowing liquid-lithium target. The resulting neutron fluxes of greater than 10/sup 14/ n/(cm/sup 2/ sec) are well collimated in the forward direction providing ...
P. Grand, K. Batchelor, J. P. Blewett, A. Goland, D. Gurinsky, J. Kukkonen, C. L. Snead   +6 more
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Experimental study of density and thermal expansion of the advanced materials and heat transfer agents for liquid metal systems of thermonuclear reactor: Lithium

High Temperature, 2011
Using the gamma-ray attenuation technique, the density of the condensed state of lithium is measured within the range from room temperature up to ∼700 K. The purity of the investigated lithium is as high as 99.95 mass %. The confidence error of experiments is within 0.3%.
S. V. Stankus, R. A. Khairulin, A. G. Mozgovoi   +2 more
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Materials for thermonuclear reactors

Journal of Nuclear Energy (1954), 1958
S. Kaufman, H.T. Miles, A.A. Ware, J. Wesson, J.L. Craston, R. Hancox, A.E. Roeson   +6 more
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Conference on Materials for Thermonuclear Reactors

Soviet Atomic Energy, 1979
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