Results 261 to 270 of about 476,906 (298)

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

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., Daenner, 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., Petrizzi, L., Pizzuto, A., Plenteda, R., Poitevin, Y., Raffray, R., Roccella, M., Roux, N., et al.   +24 more
openaire   +3 more sources

Detection of Breeding Blankets Using Antineutrinos

Science and Global Security, 2016
The Plutonium Management and Disposition Agreement between the United States and Russia makes arrangements for the disposal of 34 metric tons of excess weapon-grade plutonium. Under this agreement Russia plans to dispose of its excess stocks by processing the plutonium into fuel for fast breeder reactors.
Bernadette K. Cogswell, Patrick Huber
exaly   +3 more sources

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

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

Tritium inventory and permeation in the ITER breeding blanket

Fusion Engineering and Design, 2000
Abstract A model has allowed us to perform the analysis of the tritium inventory and permeation in the international thermonuclear experimental reactor (ITER) breeding blanket under the hypothesis of steady state conditions. Li 2 ZrO 3 (reference) and Li 2 TiO 3 (alternative) have been studied as breeding materials.
V. Violante, S. Tosti, C. Sibilia, F. Felli, S. Casadio, C. Alvani   +5 more
openaire   +1 more source

Functional materials for breeding blankets—status and developments

Nuclear Fusion, 2017
S. Konishi, M. Enoeda, M. Nakamichi, T. Hoshino, A. Ying, S. Sharafat, S. Smolentsev   +6 more
exaly   +2 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.
Massimo Zucchetti, A Ciampichetti
exaly   +3 more sources

Neutronic assessment of HCCR breeding blanket for DEMO

Fusion Engineering and Design, 2019
Abstract Helium-cooled ceramic reflector (HCCR) blanket concept was proposed as a DEMO breeding blanket in Korea. It adopted lithium ceramic breeder, graphite reflector to reduce the beryllium multiplier, reduced activation ferritic-martensitic steel as a structural material, and high pressure/temperature helium as a coolant.
Seungyon Cho, Mu-Young Ahn, Cheol Woo Lee, Jae Hyun Kim, Myeong Hyeon Woo, Jong Seong Park, Kihak Im, Youngmin Lee, Yi-Hyun Park, Dong Won Lee   +9 more
openaire   +1 more source