Results 91 to 100 of about 3,230,759 (172)

Tritium Breeding Materials

, 1984
Tritium breeding materials are essential to the operation of D-T fusion facilities. Both of the present options - solid ceramic breeding materials and liquid metal materials are reviewed with emphasis not only on their attractive features but also on ...
Hollenberg, G. W., Johnson, C. E., Abdou, M.   +2 more
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Assessments of tritium-breeding requirements and breeding potential for the STARFIRE/DEMO design [PDF]

, 1983
This paper presents assessments of tritium-breeding requirements and breeding potential for the STARFIRE/DEMO design. The assessment of breeding requirement is described based on two design considerations; i.e.: (1) tritium inventory and doubling ...
Jung, J., Abdou, M.
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Effect of divertor on tritium breeding in HELIAS [PDF]

This study presents tritium breeding calculations for the five-period helical-axis advanced stellarator (HELIAS) using the Serpent2 code. To address the absence of a detailed divertor design, a simplified divertor model with a layered homogenized ...
Lyytinen, Tommi; id_orcid, Warmer, Felix; id_orcid, Bogaarts, Timo, Snicker, Antti; id_orcid, Snicker, Antti, Warmer, Felix, Lyytinen, Tommi, Bogaarts, Timo; id_orcid   +7 more
core   +1 more source

High-Temperature Intrinsic Defect Chemistry of Li₈PbO₆ Ceramic Breeding Material. [PDF]

J Phys Chem C Nanomater Interfaces, 2023
Davies AW, Neilson WD, Bedford RT, Murphy ST.   +3 more
europepmc   +1 more source

Accelerating the engineering design of breeder blankets with parametric optimisation and sequential learning

Frontiers in Nuclear Engineering
The competing requirements of fusion breeder blankets and the high dimensionality of their design space necessitate a systematic treatment to map the variations in performance against given objective metrics and to understand the operational envelope. In
Luke Humphrey, Helen Brooks, Siddharth Mungale, Andrew Davis, David Foster   +4 more
doaj   +1 more source

Development of water-cooled cylindrical blanket in JA DEMO

Nuclear Fusion
The concept of the tritium breeding blanket for Japan’s DEMOnstration fusion reactor (JA DEMO) has been developed with pressure tightness against in-box loss-of-coolant accidents based on a water-cooled solid breeder concept.
Someya Youji, Tanigawa Hiroyasu, Sakamoto Yoshiteru, the Joint Special Design Team for Fusion DEMO   +3 more
doaj   +1 more source

Main Nuclear Responses of the DEMO Tokamak with Different In-Vessel Component Configurations

Applied Sciences
Research and development of the DEMOnstration power plant (DEMO) breeder blanket (BB) has been performed in recent years based on a predefined DEMO tritium breeding ratio (TBR) requirement, which determines a loss of wall surface due to non-breeding in ...
Jin Hun Park, Pavel Pereslavtsev
doaj   +1 more source

Optimal operation of fuel cycle of tritium plant on a daily basis

, 2017
1
LEE, IN BEUM
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Power and particle exhaust in the ST-E1 fusion power plant

Nuclear Fusion
Power exhaust challenges and potential solutions for a 5 m major radius, low-aspect ratio burning tokamak have been explored. 1D edge plasma models have been used to screen for access to detachment using short and long outer divertor legs in double and ...
M. Robinson, A. Scarabosio, E. Vekshina, J.H. Nichols, J.D. Lore, K. Borowiec, J. Varje, S.M. Levine, M. Scarpari, E.N.J. Maartensson, X. Zhang, R. Kamenicky, J. Alexander, M. Jackson, C. Marsden, S.A.M. McNamara, R. Maingi   +16 more
doaj   +1 more source

Development of tritium breeding blankets for DT-burning fusion reactors [PDF]

, 1980
This study examines the status of understanding of blanket tritium recovery and the performance of potentially viable tritium breeding materials under conditions anticipated in a DT-fueled fusion reactor environment.
Clemmer, R. G.
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