Results 231 to 240 of about 827 (260)

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

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

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

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

Tritium Breeding Capability of Heliotron-H Fusion Reactor Blankets

Journal of Nuclear Science and Technology, 1982
Atsuo Iiyoshi, Masao Ohta
exaly  

European TBM programme: First elements of RoX and technical performance assessment for DEMO breeding blankets

Fusion Engineering and Design, 2020
F Cismondi, M Zmitko, I Ricapito
exaly  

First principles review of options for tritium breeder and neutron multiplier materials for breeding blankets in fusion reactors

Fusion Engineering and Design, 2018
FRANCISCO A Hernández, P Pereslavtsev
exaly  

Materials aspects of breeding blanket design

Journal of Nuclear Materials, 1991
openaire   +1 more source