Results 271 to 280 of about 22,248 (302)

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 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

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

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

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

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

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

A STUDY OF PERMEATION BARRIERS FOR Pb17Li BREEDING BLANKETS

1991
Coatings on the surface in contact with Pb17Li can significantly decrease tritium permeation rate through structural steels and tritium inventory in the blanket. For this purpose, compatibility tests of oxidized and aluminized 316L and 1.4914 steels have been carried out up to 500°C in stagnant anisothermal Pb17Li.
A. Terlain, T. Flament, J. Sannier, J.L. Rouault   +3 more
openaire   +1 more source

MHD flow in liquid metal blankets: Major design issues, MHD guidelines and numerical analysis

Fusion Engineering and Design, 2021
C Mistrangelo, L Bühler, Sergey Smolentsev   +2 more
exaly  

A Hydrogen Sensor for Liquid-Metal Breeding Blankets

2015
In HCLL (Helium Cooled Lithium Lead) blanket for ITER fusion reactor, an efficient management operation of tritium is necessary, in order to minimize the release of tritium to the environment and to improve the economy of the overall balance of the reactor tritium inventory. In this context, optimization techniques for the measurement of tritium in the
NICOLOTTI, IURI, Utili, M., CANDIDO, LUIGI, ZUCCHETTI, MASSIMO   +3 more
openaire   +3 more sources