Results 261 to 270 of about 22,173 (305)

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
openaire   +1 more source

The manufacturing technologies of the European breeding blankets

Journal of Nuclear Materials, 2004
In the European Union, the basic manufacturing technologies have been selected for the two reference DEMO breeding blanket concepts: the helium cooled pebble bed and the helium cooled lithium lead. These technologies have been tested in the past years on small-scale samples and mock-ups, are presently under further development, and are now being ...
Cardella, A., Rigal, E., Bedel, L., Bucci, P., Fiek, C., Forest, L., Boccaccini, L., Diegele, E., Giancarli, L., Hermsmeyer, S., Janeschitz, G., Lässer, R., Li Puma, A., Lulewicz, J., Möslang, A., Poitevin, Y., Rabaglino, E.   +16 more
openaire   +3 more sources

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
openaire   +2 more sources

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
openaire   +3 more sources

Solid breeder blanket design and tritium breeding

Fusion Engineering and Design, 1991
Abstract Thermonuclear D–T power plants will have to be tritium self-sufficient. In addition to recovering the energy carried by the fusion neutrons (about 80% of the fusion energy), the blanket of the reactor will thus have to breed tritium to replace that burnt in the fusion process.
Proust, E., Anzidei, L., Dalle Donne, M., Fischer, U., Kuroda, T.   +4 more
openaire   +1 more source

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   +3 more sources

Aqueous tritium breeding blanket with natural lithium

Fusion Engineering and Design, 1989
An aqueous tritium breeding blanket concept with natural lithium has been proposed. Lithium oxide dissolved in pressurized heavy water forms a saturated solution of LiOD in the liquid phase and the remainder is suspended in the solution or forms a breeder solid skeleton.
Masabumi Nishikawa, Toshihiko Kawano, Kenzo Munakata, Yukinori Kanda, Hideki Nakashima   +4 more
openaire   +1 more source

Tritium breeding control within liquid metal blankets

Fusion Engineering and Design, 2013
Abstract A key requirement for DEMO is the on-site breeding of tritium. In order to do this, a robust control system must be employed to ensure enough tritium is being bred to sustain the fusion reactor, whilst not breeding an amount which would exceed the plant's tritium inventory license.
L. Morgan, J. Pasley
openaire   +1 more source

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

ARIES-ST breeding blanket design and analysis

Fusion Engineering and Design, 2000
Abstract ARIES-ST is a 1000 MW fusion power plant conceptual design based on a low aspect ratio ‘spherical torus’ (ST) plasma. The power core uses an advanced ‘dual-cooled’ breeding blanket with flowing PbLi breeder and He-cooled ferritic steel structures.
M.S. Tillack, X.R. Wang, J. Pulsifer, S. Malang, D.K. Sze   +4 more
openaire   +1 more source