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Diagnostic study of interface materials of co-deposition simulating impurity relevant to international thermonuclear experimental reactor by using calibration-free laser-induced breakdown spectroscopy

Spectrochimica Acta Part B: Atomic Spectroscopy, 2022
The quantitative analysis and depth profiling of a co-deposition simulating the impurity of the international thermonuclear experimental reactor (ITER) has been performed by using laser-induced breakdown spectroscopy (LIBS). In the depth profile analysis of a co-deposition of Al/W/Mo, the materials were resolved across the interfaces of layers using ...
Imran, Muhammad   +7 more
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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   +6 more
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Prospects of Using In-Containing Semiconductor Materials in Magnetic Field Sensors for Thermonuclear Reactor Magnetic Diagnostics

IEEE Transactions on Magnetics, 2013
The work presents the results of experimental investigation into the effect of neutron irradiation on thin-film magnetic field Hall sensors. It is shown that sensors based on InSb/i-GaAs heterostructures are promising for application under radiation conditions in thermonuclear reactor magnetic diagnostics systems.
Inessa Bolshakova   +10 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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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,
L. Summers
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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   +4 more
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The impact of materials selection on the design of the International Thermonuclear Experimental Reactor (ITER)

Journal of Nuclear Materials, 1994
Abstract The design being developed for the International Thermonuclear Experimental Reactor (ITER) in the Engineering Design Activities (EDA) phase has to assure the achievement of controlled ignition and extended burn, and must provide a demonstration of technologies that are essential to a reactor.
I. Team
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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   +2 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.
A. Damask
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Problem of helium in the structural materials of a thermonuclear reactor

Soviet Atomic Energy, 1982
A. S. Nikiforov   +10 more
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