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Fusion Blanket Inherent Safety Assessment [PDF]
Fusion Technology, 1986 Fusion has significant potential safety advantages. There is a strong incentive for designing fusion plants to ensure that inherent safety will be achieved. Accordingly, both the Tokamak Power Systems Studies and MINIMARS have identified inherent safety as a design goal.
Sze, D.K., Jung, J., Cheng, E.T.
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Status of Fusion Reactor Blanket Design [PDF]
Fusion Technology, 1986 This paper provides a brief review of the Blanket Comparison and Selection Study (BCSS)1 and an overview of more recent fusion reactor blanket design efforts.
Smith, D. L., Sze, D. K.
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Blanket materials for dt fusion reactors [PDF]
Journal of Nuclear Materials, 1981 Abstract This paper presents an overview of the critical materials issues that must be considered in the development of a tritium breeding blanket for a tokamak fusion reactor that operates on the D-T-Li fuel cycle. The primary requirements of the blanket system are identified and the important criteria that must be considered in the development of ...
Smith, D. L.
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Fusion blanket design and optimization techniques. [PDF]
, 2005 In fusion reactors, the blanket design and its characteristics have a major impact on the reactor performance, size, and economics. The selection and arrangement of the blanket materials, dimensions of the different blanket zones, and different requirements of the selected materials for a satisfactory performance are the main parameters, which define ...
Gohar, Y.
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Accident-tolerant hybrid ceramics for fusion breeding blanket [PDF]
Materials & DesignIn a water-cooled ceramic breeding blanket for fusion reactors, hydrogen gas generation by steam oxidation of metallic Be compounds (i.e. neutron multiplier) in a loss-of-coolant accident (LOCA) raises major safety concerns. Li–Be hybrid ceramics has a potential to reduce hydrogen generation significantly, however, the stable compositions and ...
Keisuke Mukai +3 more
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Improved Design of a Cartridge-Type Helical Blanket System for the Helical Fusion Reactor FFHR-b1 [PDF]
, 2019 0000-0002-7901-6077The cartridge-type helical blanket system called the CARDISTRY-B has been proposed for the helical fusion reactor FFHR-d1. The CARDISTRY-B is aimed at easy construction and maintenance.
NAKAGAWA, Sho +11 more
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A coupled systems code - CMHD solver for fusion blanket design [PDF]
, 2016 Fusion blankets are required to operate in a harsh environment under the influence of a number of synergistic physical phenomena, working across several length scales.
Wolfendale, Michael
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Overview on the welding technologies of CLAM steel and the DFLL TBM fabrication
Nuclear Materials and Energy, 2016 Dual Functional Lithium Lead (DFLL) blanket was proposed for its advantages of high energy exchange efficiency and on-line tritium extraction, and it was selected as the candidate test blanket module (TBM) for China Fusion Engineering Test Reactor (CFETR)
Junyu Zhang +6 more
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Progress on design and related R&D activities for the water-cooled breeder blanket for CFETR
Theoretical and Applied Mechanics Letters, 2019 : The water-cooled ceramic breeder (WCCB) blanket is one of the blanket candidates for Chinese fusion engineering testing reactor (CFETR) and is being developed at the Institute of Plasma Physics, Chinese Academy of Sciences (ASIPP).
Songlin Liu +12 more
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Nuclear Engineering and Technology, 2023 Blanket is of vital importance for engineering application of the fusion reactor. Nuclear heat deposition in materials is the main heat source in blanket structure.
Qiang Lian +11 more
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