Efficient helium cooling methods for nuclear fusion devices: Status and prospects
Само за регистроване кориснике
2009
Чланак у часопису (Објављена верзија)
Метаподаци
Приказ свих података о документуАпстракт
Helium-cooled reactors offer several important advantages as the helium is an inert and neutron transparent gas. compatible with high outlet temperatures and all structural and functional materials considered for plasma facing components. On the other hand, during the power plant studies performed up to now it became evident, that the helium pumping power could become very high if standard cooling methods based on hydraulically smooth cooling channels would be applied and that a very high heat fluxin the divertor can only be achieved when using sophisticated gas cooling methods. In relation to this the main focus in this paper is on advanced gas cooling technology applications developed at Forschungszentrum Karlsruhe (FZK)for the main in-vessel components blanket/first wall and divertor of future fusion power reactors. Among a large number of considered cooling technologies the V-rib-based surface roughness approach for the first wall and the multiple jet impingement cooling technique ...for the divertor were identified as suitable and advantageous methods. The paper presents the main parameters to be considered and an evaluation of the achievable cooling performance in both cases.
Кључне речи:
Surface roughness / Jet / Impingement / Helium / Divertor / DEMO / BlanketИзвор:
Fusion Engineering and Design, 2009, 84, 2-6, 964-968Издавач:
- Elsevier Science Sa, Lausanne
DOI: 10.1016/j.fusengdes.2009.01.008
ISSN: 0920-3796
WoS: 000267795600171
Scopus: 2-s2.0-67349099557
Институција/група
Inovacioni centarTY - JOUR AU - Ihli, T. AU - Ilić, Milica PY - 2009 UR - https://machinery.mas.bg.ac.rs/handle/123456789/925 AB - Helium-cooled reactors offer several important advantages as the helium is an inert and neutron transparent gas. compatible with high outlet temperatures and all structural and functional materials considered for plasma facing components. On the other hand, during the power plant studies performed up to now it became evident, that the helium pumping power could become very high if standard cooling methods based on hydraulically smooth cooling channels would be applied and that a very high heat fluxin the divertor can only be achieved when using sophisticated gas cooling methods. In relation to this the main focus in this paper is on advanced gas cooling technology applications developed at Forschungszentrum Karlsruhe (FZK)for the main in-vessel components blanket/first wall and divertor of future fusion power reactors. Among a large number of considered cooling technologies the V-rib-based surface roughness approach for the first wall and the multiple jet impingement cooling technique for the divertor were identified as suitable and advantageous methods. The paper presents the main parameters to be considered and an evaluation of the achievable cooling performance in both cases. PB - Elsevier Science Sa, Lausanne T2 - Fusion Engineering and Design T1 - Efficient helium cooling methods for nuclear fusion devices: Status and prospects EP - 968 IS - 2-6 SP - 964 VL - 84 DO - 10.1016/j.fusengdes.2009.01.008 ER -
@article{ author = "Ihli, T. and Ilić, Milica", year = "2009", abstract = "Helium-cooled reactors offer several important advantages as the helium is an inert and neutron transparent gas. compatible with high outlet temperatures and all structural and functional materials considered for plasma facing components. On the other hand, during the power plant studies performed up to now it became evident, that the helium pumping power could become very high if standard cooling methods based on hydraulically smooth cooling channels would be applied and that a very high heat fluxin the divertor can only be achieved when using sophisticated gas cooling methods. In relation to this the main focus in this paper is on advanced gas cooling technology applications developed at Forschungszentrum Karlsruhe (FZK)for the main in-vessel components blanket/first wall and divertor of future fusion power reactors. Among a large number of considered cooling technologies the V-rib-based surface roughness approach for the first wall and the multiple jet impingement cooling technique for the divertor were identified as suitable and advantageous methods. The paper presents the main parameters to be considered and an evaluation of the achievable cooling performance in both cases.", publisher = "Elsevier Science Sa, Lausanne", journal = "Fusion Engineering and Design", title = "Efficient helium cooling methods for nuclear fusion devices: Status and prospects", pages = "968-964", number = "2-6", volume = "84", doi = "10.1016/j.fusengdes.2009.01.008" }
Ihli, T.,& Ilić, M.. (2009). Efficient helium cooling methods for nuclear fusion devices: Status and prospects. in Fusion Engineering and Design Elsevier Science Sa, Lausanne., 84(2-6), 964-968. https://doi.org/10.1016/j.fusengdes.2009.01.008
Ihli T, Ilić M. Efficient helium cooling methods for nuclear fusion devices: Status and prospects. in Fusion Engineering and Design. 2009;84(2-6):964-968. doi:10.1016/j.fusengdes.2009.01.008 .
Ihli, T., Ilić, Milica, "Efficient helium cooling methods for nuclear fusion devices: Status and prospects" in Fusion Engineering and Design, 84, no. 2-6 (2009):964-968, https://doi.org/10.1016/j.fusengdes.2009.01.008 . .