Results 171 to 180 of about 2,502 (210)

Tritium release from lithium titanate, a low-activation tritium breeding material

Journal of Nuclear Materials, 1994
Abstract The goals for fusion power are to produce energy in as safe, economical, and environmentally benign a manner as possible. To ensure environmentally sound operation low-activation materials should be used where feasible. The ARIES Tokamak Reactor Study has based reactor designs on the concept of using low-activation materials throughout the ...
J.P. Kopasz, J.M. Miller, C.E. Johnson
openaire   +1 more source

On monitoring the tritium-breeding ratio in a fusion reactor

Plasma Devices and Operations, 2008
A concept of tritium-breeding monitoring in the DEMO reactor is discussed. A system for experimental estimation of the tritium-breeding ratio and the tritium-breeding dynamics in a helium-cooled experimental breeding submodule (EBSM) of the International Thermonuclear Expeimental Reactor is proposed.
V. Kapyshev, V. Kovalenko, V. Poliksha, A. Sidorov, YU. Strebkov, N. Yukhnov   +5 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

Neutronics Optimization of Tritium Breeding Blanket for the FDS

Plasma Science and Technology, 2002
Neutronics optimization calculations have been performed for the tritium breeding blankets with solid ceramic breeder Li2O and liquid eutectic breeder Li17Pb83, respectively, based on a 2-D geometrical configuration using the Monte Carlo neutron-photon transport code MCNP/4B.
Zheng Shan-liang, Wu Yi-can, Huang Qun-ying   +2 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

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

Overview of Analytical and Experimental Efforts on Tritium Breeding

Fusion Technology, 1985
Models have been developed and utilized to examine the conditions necessary for attaining tritium fuel self-sufficiency in fusion reactors. Results show that these conditions define important limits on the parameter space in which the plasma and various reactor components have to operate.
openaire   +1 more source

Experimental verification of tritium breeding performance of simulated aqueous slurries

The International Journal of Applied Radiation and Isotopes, 1985
An aqueous slurry of heavy water and lithium containing solids was examined to assess its merits as the tritium breeding, neutron attenuating, and heat removing portion of a first generation D-T fu...
Michael Schuller, Theodore A. Parish
openaire   +1 more source

An ICF Reactor Cavity to Maximize Tritium Breeding

Fusion Technology, 1985
Conceptual design for an ICF tritium production reactor has been completed. The cavity design is unique in that beryllium is used both as a neutron multiplier and a structural material. Neutronics calculations show the breeding ratio is over 2.0. The special problems posed by using beryllium as a structural material in a radiation environment are ...
openaire   +1 more source

MECHANICAL PROPERTIES OF LiAl02 TRITIUM BREEDING CERAMICS

1991
Mechanical strength of porous LiAlO2 ceramic materials was investigated. Ultimate compressive strength and ultimate bending strength were measured both at room temperature and at 600°C. The room temperature results corroborate previous CEA ones. No decrease of mechanical strength at 600°C is observed.
openaire   +1 more source