Results 71 to 80 of about 757 (179)

US/Japan collaborative program on fusion reactor materials: Summary of the tenth DOE/JAERI Annex I technical progress meeting on neutron irradiation effects in first wall and blanket structural materials [PDF]

, 1989
This meeting was held at Oak Ridge National Laboratory on March 17, 1989, to review the technical progress on the collaborative DOE/JAERI program on fusion reactor materials.
Rowcliffe, A. F.
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Recent progress in the development of materials for fusion reactors [PDF]

, 1991
Development of materials with suitable properties is essential if fusion is to be realized as an economic, safe, and environmentally acceptable energy source.
Bloom, E. E., Rowcliffe, A. F.
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Magnetic fusion energy materials technology program, annual progress report for period ending June 30, 1976

, 1976
Activities in research programs are reported on materials for use in thermonuclear reactor development. Information and data are included on radiation effects on stainless steel 316, nickel-base alloys, molybdenum-base alloys, vanadium alloys, and SAP ...
Scott, J. L. (comp.)
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First operation with the JET International Thermonuclear Experimental Reactor-like wall

, 2013
To consolidate International Thermonuclear Experimental Reactor (ITER) design choices and prepare for its operation, Joint European Torus (JET) has implemented ITER's plasma facing materials, namely, Be for the main wall and W in the divertor.
G. J. van Rooij, Sips, A.C.C., Contributors, JET-EFDA, M. Lehnen, D. van Eester, Dux, R., Hobirk, J., Loarer, T., Bucalossi, J., E. de la Luna, Neu, R., Giroud, C., M. Beurskens, M. Groth, Lehnen, M., G. Maddison, Sips, A., P. C. de Vries, JET-EFDA Contributors, Brezinsek, S., Coenen, J., C. Maggi, J. W. Coenen, Eester, D., A. Meigs, Beurskens, M., P. Lomas, Matthews, G., S. Brezinsek, Mayoral, M., Sips, A. C. C., van Rooij, G.J., Coenen, J.W., Luna, E., G. Matthews, Maddison, G., Mertens, Ph., de Vries, P. C., Challis, C., Philipps, V., Vries, P., Arnoux, G., Mertens, P., Lerche, E., Maggi, C., Calabro, G., C. Challis, S. Marsen, Nunes, I., Rimini, F., Marsen, S., V. Bobkov, Frassinetti, L., G. Calabro, Lomas, P., C. Giroud, P. Lang, Pütterich, T., Joffrin, E., M.-L. Mayoral, I. Nunes, Mayoral, M. -L, van Eester, D., J. Hobirk, Coenen, J. W., G. van Rooij, Sieglin, B., A. C. C. Sips, Meigs, A., Mayoral, M.-L., J. Bucalossi, E. Lerche, de Vries, P.C., de la Luna, E., M. Sertoli, L. Frassinetti, R. Dux, V. Philipps, Mayoral, M-L, Frassinetti, Lorenzo,, Lang, P., T. Pütterich, T. Loarer, Bobkov, V., Sertoli, M., van Rooij, G., G. Arnoux, Ph. Mertens, M-L Mayoral, Rooij, G., B. Sieglin, Groth, M., E. Joffrin, F. Rimini, R. Neu   +94 more
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Study on Application Characteristic of Hot-pressing B4C Block in ITER Diagnostic Equatorial Port 12

Yuanzineng kexue jishu
The diagnostic equatorial port 12 (EQ#12) of the International Thermonuclear Experimental Reactor (ITER) integrates plasma diagnostic systems for observing and providing feedback on plasma operating conditions.
HU Xiaoyue1, 2, WANG Xudi1, HU Qingsheng2, XU Changjun2, PEI Yanbin3, YANG Chuansen4, ZHAO Junyu2
doaj   +1 more source

US ITER (International Thermonuclear Experimental Reactor) shield and blanket design activities

, 1988
This paper summarizes nuclear-related work in support of the US effort for the International Thermonuclear Experimental Reactor (ITER) Study. Primary tasks carried out during the past year include design improvements of the inboard shield developed for ...
Baker, C. C.
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Fabrication, properties, and tritium recovery from solid breeder materials [PDF]

, 1991
The breeding blanket is a key component of the fusion reactor because it directly involves tritium breeding and energy extraction, both of which are critical to development of fusion power.
Tanaka, S. (Tokyo Univ. (Japan)), Kondo, T. (Japan Atomic Energy Research Inst., Tokyo (Japan)), Roux, N. (CEA Centre d'Etudes Nucleaires de Saclay, 91 - Gif-sur-Yvette (France)), Johnson, C.E. (Argonne National Lab., IL (USA)), Vollath, D. (Kernforschungszentrum Karlsruhe GmbH (Germany, F.R.))   +4 more
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The International Thermonuclear Experimental Reactor (ITER): Design and materials selection [PDF]

, 1989
The success of ITER relies on aggressive design of the superconducting magnet systems. This design emphasized high radiation-damage tolerance, acceptance of high nuclear heat loads, and high operational stresses in the Toroidal Field (TF) magnets.
Heim, J. R., Miller, J. R., Summers, L. T.   +2 more
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Irradiation Effect on the Interface of the Composites Used as the Insulation Materials in the Nuclear Fusion Reactor

, 2014
In ITER (International Thermonuclear Experimental Reactor), the insulation materials containing polymeric matrix are the most radiation-sensitive among the materials constituting the superconducting magnet in the nuclear fusion reactor.
Mishima, F., Nishijima, S., Hayashi, M., Nakata, Y., Akiyama, Y.   +4 more
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Corrosion studies of a stainless steel structure for the ITER (International Thermonuclear Experimental Reactor) aqueous lithium salt blanket concept

, 1990
The aqueous lithium slat blanket (ALSB) employs water, with a dissolved lithium compound, as both the coolant and tritium breeding medium. The ALSB concept is one of three blanket options currently being examined for breeding tritium in the International
Wrisley, K.L., Motyka, E., Duquette, D.J., Steiner, D., Embrechts, M.J.   +4 more
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