Results 151 to 160 of about 757 (179)

Abstract: Tritium diffusion in ceramic materials for thermonuclear reactors

Journal of Vacuum Science and Technology, 1976
Tritium diffusion coefficients have been measured in ceramic materials of potential interest as insulator or wall materials in controlled thermonuclear reactors. Tritium was recoil injected into samples to about 2×1014 atoms/cm2 through thermal‐neutron transmutation of a surface blanket of 6Li‐enriched Li2CO3 in the NCSU Pulstar research reactor ...
J. D. Fowler, R. A. Causey, D. Chandra, T. S. Elleman, K. Verghese   +4 more
openaire   +1 more source

Protective nitrided layers for the structural materials of thermonuclear reactors

Soviet Atomic Energy, 1987
Application of protective coatings based on light elements having strong interatomic bonds is one of the most practical and promising methods of decreasing the rate of erosion (wear) of the first wall of thermonuclear reactors due to ion sputtering and blistering.
I. N. Afrikanov, E. K. Baranova, M. I. Guseva, M. G. Isakov, P. P. Shiryaev   +4 more
openaire   +1 more source

Investigation of ferromagnetic phase precipitation on the surface of some constructional materials for thermonuclear reactors

Journal of Nuclear Materials, 1981
Abstract Austenitic stainless steels are considered as a prospective material for the first wall of the thermonuclear reactors. Radiation and temperature influence erosion of material, and contamination of the plasma. This paper describes the results of investigations on the process of ferromagnetic layer formation on the surface of Cr-Mn and Cr-Ni ...
E.M. Lazarev, N.A. Korotkov, G.S. Krintchik, L.V. Nikitin, G.G. Bondarenko, G.M. Feditchkin   +5 more
openaire   +1 more source

Sputtering Measurements on Controlled Thermonuclear Reactor Materials Using Auger Electron Spectroscopy

Nuclear Technology, 1976
Simultaneous auger electron spectroscopy and ion sputtering have been used to measure the sputter yield, S (atom/ion), for Ar/sup +/ on carbon, tungsten, niobium, and silver in the energy range from 0.5 to 1.5 keV and for H/sup +/ on tungsten, carbon, and silver at 11 keV.
Joe N. Smith, C. H. Meyer, J. K. Layton
openaire   +1 more source

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,
openaire   +1 more source

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
openaire   +1 more source

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
openaire   +1 more source

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
openaire   +2 more sources

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
openaire   +1 more source

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
openaire   +1 more source