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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.   +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.   +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   +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   +4 more
openaire   +1 more source

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   +24 more
openaire   +1 more source

High Performance Breeding Blankets for ICF Facilities

Nuclear Technology - Fusion, 1983
Discussed are the advantages of using fusion neutrons for breeding special nuclear materials and tritium. Monte Carlo calculations were used to identify both fissionable and nonfissionable materials that multiply neutrons and increase breeding ratios. Fissionable multipliers also greatly multiply the neutron energy.
A. R. Larson, I. O. Bohachevsky
openaire   +1 more source

LAYERED PEBBLE BED CONCEPT FOR ITER BREEDING BLANKET

1993
Design efforts have been continued to refine and simplify the layered pebble bed design for the ITER breeding blanket. Detailed neutronics and thermal analyses were conducted to investigate the optimal configuration. Static and dynamic stress analyses were carried out to examine stress and deformation of the blanket box structure under disruption ...
H. Takatsu   +11 more
openaire   +1 more source

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