Calculation of the Heat Flux on the First Wall During Disruption on Tokamak
Sign Up to like & getrecommendations! Published in 2017 at "Journal of Fusion Energy"
DOI: 10.1007/s10894-016-0118-6
Abstract: Disruptions are the most dangerous instabilities in tokamak plasma. During plasma disruption, the large amounts of energy will be deposited on Plasma Facing Components (PFCs) which is a damaging threat for the divertor target and… read more here.
Keywords: divertor; disruption; first wall; heat ... See more keywords
Thermo-mechanical analyses and ways of optimization of the helium cooled DEMO First Wall under RCC-MRx rules
Sign Up to like & getrecommendations! Published in 2017 at "Fusion Engineering and Design"
DOI: 10.1016/j.fusengdes.2016.12.040
Abstract: Abstract The EUROfusion Consortium develops a design of a fusion power demonstrator plant (DEMO) in the framework of the European “Horizon 2020” innovation and research program. One of the key components in the fusion reactor… read more here.
Keywords: helium cooled; rcc mrx; demo; first wall ... See more keywords
Melting and evaporation analysis of the first wall in a water-cooled breeding blanket module under vertical displacement event by using the MARS code
Sign Up to like & getrecommendations! Published in 2017 at "Fusion Engineering and Design"
DOI: 10.1016/j.fusengdes.2017.02.110
Abstract: Abstract Plasma facing components of tokamak reactors such as ITER or the Korean fusion demonstration reactor (K-DEMO) can be subjected to damage by plasma instabilities. Plasma disruptions like vertical displacement event (VDE) with high heat… read more here.
Keywords: module; blanket; analysis; evaporation ... See more keywords
Effect of ELMS and disruptions on FNSF plasma-facing components
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DOI: 10.1016/j.fusengdes.2017.07.022
Abstract: Abstract Previous work has addressed the thermomechanical and electromagnetic effects of ELMs and disruptions on plasma-facing components in conceptual, commercial fusion reactors. Given that the proposed Fusion Nuclear Science Facility (FNSF) will have different geometry… read more here.
Keywords: facing components; effect; plasma facing; first wall ... See more keywords
Thermal mechanical characteristics of blanket first walls with different cooling channel shapes
Sign Up to like & getrecommendations! Published in 2018 at "Fusion Engineering and Design"
DOI: 10.1016/j.fusengdes.2018.01.032
Abstract: Abstract A water-cooled ceramic breeder blanket has been developed. Heat flux and coolant pressure are applied to the first wall of the blanket in a fusion reactor. A square cooling channel is adopted in the… read more here.
Keywords: thermal mechanical; cooling channel; channel shapes; first wall ... See more keywords
Investigation of edge impurity transport derived from the first wall on EAST with EMC3-EIRENE modelling
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DOI: 10.1016/j.fusengdes.2018.03.060
Abstract: Abstract The long-term operations of the EAST experiments result in a substantial redeposition of impurities on the first wall, which is considered as the potential impurity source during the discharge. The transport properties of lithium… read more here.
Keywords: emc3 eirene; impurity source; transport; first wall ... See more keywords
EU contribution to the procurement of blanket first wall and divertor components for ITER
Sign Up to like & getrecommendations! Published in 2018 at "Fusion Engineering and Design"
DOI: 10.1016/j.fusengdes.2018.04.050
Abstract: Abstract Fusion for Energy (F4E), the European Domestic Agency for ITER, is responsible for a significant share of the overall procurement of internal components inside the vacuum vessel, the largest ones being as follows: (1)… read more here.
Keywords: first wall; blanket first; contribution procurement; procurement ... See more keywords
Development and validation of the blanket First Wall mock-up model in RELAP5-3D
Sign Up to like & getrecommendations! Published in 2018 at "Fusion Engineering and Design"
DOI: 10.1016/j.fusengdes.2018.05.050
Abstract: Abstract In the frame of the development of the equatorial outboard blanket module of the EU DEMO (Demonstration Fusion Power Plant) blanket concepts, the qualification and testing of mock-ups are foreseen by means of different… read more here.
Keywords: development validation; blanket; model; first wall ... See more keywords
Thermo-mechanical stress analysis of the water cooled DEMO First Wall mock-up components
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DOI: 10.1016/j.fusengdes.2018.05.072
Abstract: Abstract The European DEMOnstration (DEMO) reactor precedes the development of the fully commercial fusion power plant. One of the key components of the DEMO is the first wall (FW). The FW is acted upon by… read more here.
Keywords: water; stress analysis; demo; demo first ... See more keywords
DEMO First Wall misalignment study
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DOI: 10.1016/j.fusengdes.2019.04.046
Abstract: Abstract Within the DEMO first wall 3D shape design activity, studying the effect of misalignment started in 2017. Such assessments have been conducted in the past for ITER and heat flux penalty factor maps have… read more here.
Keywords: heat; heat flux; demo first; effect ... See more keywords
Development of a WCLL DEMO First Wall design module in the SYCOMORE system code interfaced with the neutronic one
Sign Up to like & getrecommendations! Published in 2020 at "Fusion Engineering and Design"
DOI: 10.1016/j.fusengdes.2020.111514
Abstract: Abstract The pre-conceptual design of the DEMOnstration reactors has already started and several tokamak configurations have to be tested to find the best design by exploring different design parameters. Fast simulations involving the different components… read more here.
Keywords: sycomore system; wall design; first wall; system code ... See more keywords