Results 221 to 230 of about 827 (260)

TRITIUM BREEDING CALCULATION IN A STELLARATOR BLANKET

Problems of Atomic Science and Technology, 2019
In current blanket projects, tritium breeding ratio (TBR), the ratio of tritium production rate to the neutron production rate, is low (1.1…1.2). The MCNPX Monte-Carlo code has been used to model the neutron kinetics and to look for a principal possibility of increase TBR within a stellarator blanket limited space.
Chernitskiy, S.V., Moiseenko, V.E.
openaire   +2 more sources

ITER reference breeding blanket design

Fusion Engineering and Design, 1999
The ITER reference breeding blanket design is water-cooled and is characterised by the use of the neutronic multiplier and breeder materials in the form of pebbles. Besides the achievement, with margin, of the tritium breeding ratio (TBR) minimum requirement, it exhibits an internal layout allowing it to withstand properly electromagnetic loads during ...
Ferrari, M., Bianchi, A., Celentano, G., Dänner, W., Enoeda, M., Gerber, A., Gohar, Y., Gulden, W., Ioki, K., Kuroda, T., Lopatkin, A., Lucca, F., Masson, X., Mattas, R., Mazzone, G., Mustoe, J., Parker, R. R., Petrizzi, L., Pizzuto, A., Plenteda, R., Poitevin, Y., Raffray, R., Roccella, M., Roux, N., Scaffidi-Argentina, F., Simoneau, J. P., Strebkov, Y., Zacchia, F.   +27 more
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A breeding blanket in ITER-FEAT

Fusion Engineering and Design, 2003
Abstract At the beginning of life ITER-FEAT will be equipped with a shielding blanket; nevertheless since many advantages can be envisaged in having a breeding blanket in the machine, such a concept has been investigated as well. It is a water-cooled blanket in which both ceramic breeder and beryllium multiplier are present in the form of single ...
Nardi, C., Petrizzi, L., Piazza, G.
openaire   +2 more sources

Multilayered Blanket Concept for Tritium Breeding Assemblies Blanket Engineering

Nuclear Technology - Fusion, 1983
The multilayered concept of the fusion blanket is introduced, and it is shown that with this concept the lithium inventory can be reduced by an order of magnitude compared to that in the block conc...
Vijay R. Nargundkar, Om Prakash Joneja
openaire   +1 more source

Breeding blanket concepts for fusion and materials requirements

Journal of Nuclear Materials, 2002
This paper summarizes the design and performances of recent breeding blanket concepts and identifies the key material issues associated with them. An assessment of different classes of concepts is carried out by balancing out the potential performance of the concepts with the risk associated with the required material development.
Raffray, A. R., Akiba, M., Chuyanov, V., Giancarli, L., Malang, S.   +4 more
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Compatibility problems in tritium breeding blankets

Journal of Nuclear Materials, 1991
Abstract The compatibility between tritium breeding materials (liquid or solid), neutron multiplier and structural steels is a concern for the choice of a tritium breeding blanket for NET. For solid tritium breeding blanket, it seems that the more severe compatibility problem is due to the interaction of beryllium with steel.
M. Broc, T. Flament, A. Terlain, J. Sannier   +3 more
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Thermal mechanical analysis of a solid breeding blanket

Fusion Engineering and Design, 2003
Abstract This paper deals with a theoretical model of thermal mechanical behaviour of pebble beds, used as neutron multiplier or tritium breeder in the breeding blanket of a fusion nuclear reactor. The model tries to sum up the advantages of the two approaches (‘discrete’ method and macroscopic method), presently used for analysing the pebble bed ...
openaire   +2 more sources

Status of the European breeding blanket technology

Fusion Engineering and Design, 1997
Abstract This paper presents an overview of the activities within European laboratories on the development of breeding blankets for a DEMO reactor which are presently focused on the two selected blanket lines, the Water-Cooled Lithium–Lead (WCLL) blanket and the Helium-Cooled Pebble-Bed (HCPB) blanket.
L Giancarli, M Dalle Donne, W Dietz
openaire   +1 more source

Tritium permeation issues for helium-cooled breeding blankets

2013 IEEE 25th Symposium on Fusion Engineering (SOFE), 2013
Tritium permeation through Breeding Blanket and Steam Generator heat transfer areas is a crucial aspect for the design of the next generation DEMO fusion power plants. Tritium is generated inside the breeder, dissolves in and permeates through materials, thus leading to a potential hazard for the environment.
Franza F., Boccaccini L. V., Demange D., CIAMPICHETTI, ANDREA, ZUCCHETTI, MASSIMO   +4 more
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The European breeding blanket design for ITER

17th IEEE/NPSS Symposium Fusion Engineering (Cat. No.97CH36131), 2002
In the frame of the ITER Engineering Design Activity (EDA), the European Home Team (EU HT), in collaboration with the Joint Central Team (JCT) and the three other HTs, has contributed to the development of a joint water-cooled solid breeder blanket design concept for the ITER Enhanced Performance Phase.
M. Ferrari, W. Danner, A. Bianchi, G. Celentano, D. Cepraga, A. Cheyne, M.D. Donne, L. De Stefanis, M. Eid, J.-M. Gay, W. Gulden, H. Jahn, F. Lucca, X. Masson, G. Mazzone, J. Mustoe, L. Petrizzi, T. Pinna, M. Pirozzi, A. Pizuto, Y. Poitevin, M. Roccella, F. Scaffidi-Argentina, D. Sherwood, F. Zacchia   +24 more
openaire   +1 more source