Results 191 to 200 of about 571,720 (260)

TRITIUM BREEDING CALCULATION IN A STELLARATOR BLANKET

Problems of Atomic Science and Technology, 2019
In current blanket projects, tritium breeding ratio (TBR), the ratio of tritium production rate to the neutron production rate, is low (1.1…1.2). The MCNPX Monte-Carlo code has been used to model the neutron kinetics and to look for a principal possibility of increase TBR within a stellarator blanket limited space.
Chernitskiy, S.V., Moiseenko, V.E.
openaire   +2 more sources

Tritium fuel cycle modeling and tritium breeding analysis for CFETR

Fusion Engineering and Design, 2016
Abstract Attaining tritium self-sufficiency is a critical goal for fusion reactor operated on the D–T fuel cycle. The tritium fuel cycle models were developed to describe the characteristic parameters of the various elements of the tritium cycle as a tool for evaluating the tritium breeding requirements.
Hongli Chen, Lei Pan, Zhongliang Lv, Wei Li, Qin Zeng   +4 more
openaire   +1 more source

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.
Franza F., Boccaccini L. V., Demange D., CIAMPICHETTI, ANDREA, ZUCCHETTI, MASSIMO   +4 more
openaire   +4 more sources

Properties and performance of tritium breeding ceramics

Journal of Nuclear Materials, 1992
Lithium-containing ceramics are being strongly considered as tritium breeding materials for fusion reactor blankets owing to their good thermal stability, favorable chemical behavior and tritium breeding potential, and excellent tritium release characteristics. The research effort has focused on four compounds: Li 2 O, γ-LiAIO 2 , Li 4 SiO 4 , and Li 2
N. Roux, C. Johnson, K. Noda
openaire   +2 more sources

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

Behaviour of tritium in breeding materials

Fusion Engineering and Design, 2005
Abstract The tritium release from ceramic materials of the HCPB under real DEMO operating conditions will depend not only on temperature and neutron flux but also on an intense magnetic field (MF) of 7–9 T. The delay in the tritium release induced by the MF is proportional to the grain size of the ceramics, the squared MF intensity and the abundance ...
G. Kizāne, J. Tīliks, A. Vītiņš, J. Tīliks, J. Rudzītis   +4 more
openaire   +1 more source

Tritium Transport in WCLL Outboard Breeding Blanket of EU-DEMO Reactor Under Pulsed Plasma Operation

Fusion science and technology, 2023
The accurate prediction of the tritium inventory and permeation fluxes in the water-cooled lithium-lead (WCLL) breeding blanket of the European DEMO fusion reactor is a key aspect for future thermonuclear power plant licensing. In this context, a tritium
L. Candido, C. Alberghi, P. Arena, F. Moro, S. Noce, M. Utili, M. Zucchetti   +6 more
semanticscholar   +1 more source

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

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