Results 261 to 270 of about 200,079 (309)

Physicochemical processes in blanket ceramic materials

Fusion Engineering and Design, 2003
Abstract Effect of external magnetic field (MF) on important physicochemical processes in ceramic blanket materials, the Li4SiO4 (FZK) and Li2TiO3 (CEA) ceramic pebbles, was studied. Stoichiometric amounts of the radiation-induced defects (RD) of the electron and hole type form at radiolysis of the ceramic materials.
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Development of advanced blanket materials for a solid breeder blanket of a fusion reactor

Nuclear Fusion, 2003
The design of an advanced solid breeding blanket in a DEMO reactor requires a tritium breeder and a neutron multiplier that can withstand high temperatures and high neutron fluences, and the development of such advanced blanket materials has been carried out by collaboration between JAERI, universities and industries in Japan.
H Kawamura, E Ishitsuka, K Tsuchiya, M Nakamichi, M Uchida, H Yamada, K Nakamura, H Ito, T Nakazawa, H Takahashi, S Tanaka, N Yoshida, S Kato, Y Ito   +13 more
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Tritium recovery from liquid Li17Pb83 alloy blanket material

Nuclear Engineering and Design. Fusion, 1984
Abstract Two methods to recover the tritium from the Li 17 Pb 83 liquid breeder used in the breeding blanket design developed at JRC-Ispra for INTOR/NET [1] are outlined and discussed. They are (i) direct tritium pumping from stagnant and stirred breeder, and (ii) tritium extraction from a packed or bubble column by flushing an inert gas in counter ...
G. Pierini, A.M. Polcaro, P.F. Ricci, A. Viola   +3 more
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SEAL Studies of Variant Blanket Concepts and Materials

Journal of Fusion Energy, 1997
Within the European SEAL (Safety and Environmental Assessment of fusion power, Long-term) program, safety and environmental assessments have been performed which extend the results of the earlier SEAFP (Safety and Environmental Assessment of Fusion Power) program to a wider range of blanket designs and material choices.
I. Cook, N. P. Taylor, C. B. A. Forty, W. E. Han   +3 more
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Low cycle fatigue behavior of blanket structural materials

Journal of Nuclear Materials, 1979
Low cycle fatigue behavior of 316 austenitic stainless steel, niobium, Nb-1Zr and sintered molybdenum, candidate materials for the first wall and blanket structural components of fusion reactors, was investigated. Fatigue tests were conducted in a vacuum in the temperature range from 298 K to 1273 K.
N. Nagata, K. Furuya, R. Watanabe
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Ion beam analyses for Li2TiO3 blanket candidate material

Nuclear Instruments and Methods in Physics Research Section B: Beam Interactions with Materials and Atoms, 2014
Abstract Combined NRBS (non-Rutherford backscattering spectroscopy) and NRA (nuclear reaction analysis) methods have been applied to Li 2 CO 3 samples with Li of various isotopic compositions. Densities of the component elements as well as the isotopic composition of Li have been determined within an error of about 10% or less.
Yuichi Furuyama, Sho Kawatsu, Akira Taniike, Akira Kitamura   +3 more
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Fusion First-Wall/Blanket Materials

1981
At first sight it might appear somewhat incongruous that a discussion on CTR materials should be included in what is admittedly a fission-reactordominated work. However, the intent here is not to embark on a detailed discussion of CTR materials development (which could fill a book in itself) but, rather, to continue the theme developed in preceding ...
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ITER R & D on breeder blanket materials

Journal of Nuclear Materials, 1991
The International Thermonuclear Experimental Reactor (ITER) activity includes specific RD viz., European Community, Japan, Soviet Union and the United States. The current effort includes several subtasks in each of the following four task areas: 1. (1) ceramic breeder materials, 2. (2) lead-lithium breeder, 3. (3) aqueous salt solutions,
D.L. Smith, W. Daenner, G. Kalinin, H. Yoshida   +3 more
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Vanadium alloys as structural materials for fusion reactor blanket

Plasma Devices and Operations, 1996
Abstract The results of the investigations of vanadium-base alloys which are considered as perspective material for the first wali and tritium blanket of thermonuclear reactor are given. Data for the influence of alloying on the metallurgical technological effectiveness, mechanical properties, radiation resistance and corrosion of the alloys in lithium,
S. N. Votinov, M. I. Solonin, A. D. Nikulin, A. B. Alekseev, Yu. I. Kazennov, V. P. Kondrat'ev, M. M. Potapenko, V. M. Tebus, V. I. Khrustalev   +8 more
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Current Status of Beryllium Materials for Fusion Blanket Applications

Fusion Science and Technology, 2014
Beryllium is a promising functional material for several breeder system concepts to be tested within the experimental fusion reactor ITER and, later, implemented in the first commercial demonstrati...
Vladimirov, P., Bachurin, D., Borodin, V., Chakin, V., Ganchenkova, M., Fedorov, A., Klimenkov, M., Kupriyanov, I., Moeslang, A., Nakamichi, M., Shibayama, T., Van Til, S., Zmitko, M.   +12 more
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