Results 21 to 30 of about 199,939 (310)
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 ...
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Testing the use of bomb radiocarbon to date the surface layers of blanket peat [PDF]
, 2004 The recently formed surface layers of peatlands are archives of past environmental conditions and can have a temporal resolution considerably greater than deeper layers.
Garnett, M.H., Stevenson, A.C.
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Energies, 2016 The qualification and validation of nuclear technologies are daunting tasks for fusion demonstration (DEMO) and power plants. This is particularly true for advanced designs that involve harsh radiation environment with 14 MeV neutrons and high ...
Laila El-Guebaly +3 more
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Concept of a fast breeder reactor to transmute MAs and LLFPs
Scientific Reports, 2021 The long-term issues of nuclear power systems are the effective use of uranium resources and the reduction of radioactive waste. Important radioactive wastes are minor actinides (MAs: 237Np, 241Am, 243Am, etc.) and long-lived fission products (LLFPs ...
Toshio Wakabayashi
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Thermodynamic Performance of Ceramic Tritium Breeding Blanket Material [PDF]
Fusion Technology, 1986 Thermodynamic calculations have been made to compare the thermochemical performance of three candidate breeder blanket materials, Li/sub 2/O, LiAlO/sub 2/, and Li/sub 4/SiO/sub 4/. These calculations were done for the temperature range of 900 to 1300/sup 0/K and the oxygen activity range of 10/sup -25/ to 10/sup -5/.
Johnson, C. E., Fischer, A. K.
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Surface quality of products with heterogeneous coatings during mechanical processing
Весці Нацыянальнай акадэміі навук Беларусі: Серыя фізіка-тэхнічных навук, 2019 It is shown that when machining products from materials with heterogeneous structure, possibilities of management of a condition of a blanket are significantly limited.
S. A. Chizhik +12 more
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IFMIF suitability for evaluation of fusion functional materials [PDF]
, 2011 The International FusionMaterials Irradiation Facility (IFMIF) is a future neutron source based on the D-Li stripping reaction, planned to test candidate fusionmaterials at relevant fusion irradiation conditions.
A. García +25 more
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EPJ Web of Conferences, 2020 This paper presents an overview of the main challenges that fusion research is facing on the road to a demonstration power plant. The focus is on magnetic confinement fusion.
Romanelli Francesco
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Integrated Material System Modeling of Fusion Blanket
MATERIALS TRANSACTIONS, 2013 1National Institute for Fusion Science, Toki 509-5292, Japan 2Sandia National Laboratories, Albuquerque, NM 87123-1129, USA 3Shimane University, Matsue 690-8504, Japan 4University of Californian, San Diego, CA 92093-0417, USA 5Kyushu University, Fukuoka 812-8581, Japan 6Shizuoka University, Shizuoka 422-8529, Japan 7Department of Materials Science and ...
A. Sagara +11 more
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Conceptual design of the EU-DEMO dual coolant lithium lead equatorial module [PDF]
, 2016 © 20xx IEEE. Personal use of this material is permitted. Permission from IEEE must be obtained for all other uses, in any current or future media, including reprinting/republishing this material for advertising or promotional purposes, creating new ...
Fernández, I. +6 more
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