Results 31 to 40 of about 967,607 (110)
Status of fusion reactor blanket design [PDF]
, 1986 The recent Blanket Comparison and Selection Study (BCSS), which was a comprehensive evaluation of fusion reactor blanket design and the status of blanket technology, serves as an excellent basis for further development of blanket technology.
Sze, D. K., Smith, D. L.
core
Nuclear FusionThe breeding blanket is a critical component of magnetic confinement fusion reactors. The reliability, availability, maintainability, and inspectability (RAMI) of the blanket has been recognized as a major challenge on the pathway to commercial fusion ...
Qingzhu Liang +4 more
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The investigation of the neutronic responses of components in the K-DEMO
Nuclear Fusion, 2023 The neutronic response of consisting materials of the Korean fusion DEMOnstration reactor (K-DEMO) in its fusion neutron environment is a crucial consideration factor from the conceptual design stage of the K-DEMO.
Byung Chul Kim
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Technical issues for beryllium use in fusion blanket applications [PDF]
, 1985 Beryllium is an excellent non-fissioning neutron multiplier for fusion breeder and fusion electric blanket applications. This report is a compilation of information related to the use of beryllium with primary emphasis on the fusion breeder application ...
Fulton, F. J. +17 more
core +1 more source
Simplified calculations of tritium production in a lithium-lead blanket for a fusion reactor'
, 1990 The tritium production rate in a DEMO fusion-reactor blanket with Li17Pb83 liquid breeder has been calculated. Tritium production in a blanket is the result of many material and geometric characteristics of the machine; some of these have been optimized,
Zucchetti, Massimo
core +1 more source
Nuclear fusion waste classification of K-DEMO under the Korean radioactive waste regulations
Nuclear Fusion, 2022 The nuclear fusion waste generated by the activation of the constitutent components of the Korean fusion DEMOnstration reactor (K-DEMO) is assessed after the end of life (EOL).
Byung Chul Kim
doaj +1 more source
Fusion blanket inherent safety assessment [PDF]
, 1986 The inherent safety aspect of TPSS reactor blankets has been investigated. The idea is to design the blanket so safe that cost savings can be realized such as through non-nuclear grading construction.
Sze, D.K., Jung, J., Cheng, E.T.
core
Sensitivity of the first-wall radiation damage to fusion reactor blanket composition [PDF]
, 1977 The atomic displacement and hydrogen and helium gas production rates in a 1-cm-thick type-316 stainless steel first wall have been calculated as a function of blanket composition in a typical one-dimensional fusion reactor model.
Gabriel, T. A. +2 more
core +1 more source
Loss of power accident analysis for the HCCR blanket
Nuclear Engineering and TechnologyThe blanket system is a crucial element in nuclear fusion power generation, tasked with tritium production and the efficient dissipation of the high thermal flux from the tokamak. Korea is in the process of developing the Helium Cooled Ceramic Reflector (
Hyung Gon Jin +3 more
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Cm-244 as Multiplier and Breeder in a ThO2 Hybrid Blankets of Deuterium-Tritium Driven Source
Journal of King Saud University: Engineering Sciences, 1990 The safeguard aspects of Cm-244 - a nuclear waste product in LWRs – in a cylindrical hybrid blanket driven by a (D,T) fusion neutron source have been analyzed.Cm-244 has been investigated for two different applications: 1. As a neutron multiplier between
Tawfik A. Al-Kusayer
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