Thermohydraulic experimental design for the European Helium-Cooled-Pebble-Bed Test Blanket Module
Само за регистроване кориснике
2008
Чланак у часопису (Објављена верзија)
Метаподаци
Приказ свих података о документуАпстракт
The peculiarities of the coolant flow in Helium-Cooled-Pebble-Bed Test Blanket Module (TBM) are (i) very intensive heating of the first wall from the plasma side and (ii) very complicated geometry of How domain consisting of large coolant collectors with numerous flow obstacles and long narrow channels meandering in the first wall, cap, stiffening and cooling plates. In relation to this, at the institute for Reactor Safety in Forschungszentrum Karlsruhe two thermohydraulic aspects of TBM coolant system are investigated: heat removal from the first wall in the framework of HETRA experiment and mass flow distribution among different components of the TBM coolant system in GRICAMAN experiments. This paper presents the design of corresponding experimental facilities.
Кључне речи:
Test blanket module / Heat transfer / Flow distribution / Experimental facilitiesИзвор:
Fusion Engineering and Design, 2008, 83, 7-9, 1253-1257Издавач:
- Elsevier Science Sa, Lausanne
DOI: 10.1016/j.fusengdes.2008.05.031
ISSN: 0920-3796
WoS: 000262224100078
Scopus: 2-s2.0-56949103687
Институција/група
Inovacioni centarTY - JOUR AU - Ilić, Milica AU - Kiss, Bela AU - Ihli, T. PY - 2008 UR - https://machinery.mas.bg.ac.rs/handle/123456789/827 AB - The peculiarities of the coolant flow in Helium-Cooled-Pebble-Bed Test Blanket Module (TBM) are (i) very intensive heating of the first wall from the plasma side and (ii) very complicated geometry of How domain consisting of large coolant collectors with numerous flow obstacles and long narrow channels meandering in the first wall, cap, stiffening and cooling plates. In relation to this, at the institute for Reactor Safety in Forschungszentrum Karlsruhe two thermohydraulic aspects of TBM coolant system are investigated: heat removal from the first wall in the framework of HETRA experiment and mass flow distribution among different components of the TBM coolant system in GRICAMAN experiments. This paper presents the design of corresponding experimental facilities. PB - Elsevier Science Sa, Lausanne T2 - Fusion Engineering and Design T1 - Thermohydraulic experimental design for the European Helium-Cooled-Pebble-Bed Test Blanket Module EP - 1257 IS - 7-9 SP - 1253 VL - 83 DO - 10.1016/j.fusengdes.2008.05.031 ER -
@article{ author = "Ilić, Milica and Kiss, Bela and Ihli, T.", year = "2008", abstract = "The peculiarities of the coolant flow in Helium-Cooled-Pebble-Bed Test Blanket Module (TBM) are (i) very intensive heating of the first wall from the plasma side and (ii) very complicated geometry of How domain consisting of large coolant collectors with numerous flow obstacles and long narrow channels meandering in the first wall, cap, stiffening and cooling plates. In relation to this, at the institute for Reactor Safety in Forschungszentrum Karlsruhe two thermohydraulic aspects of TBM coolant system are investigated: heat removal from the first wall in the framework of HETRA experiment and mass flow distribution among different components of the TBM coolant system in GRICAMAN experiments. This paper presents the design of corresponding experimental facilities.", publisher = "Elsevier Science Sa, Lausanne", journal = "Fusion Engineering and Design", title = "Thermohydraulic experimental design for the European Helium-Cooled-Pebble-Bed Test Blanket Module", pages = "1257-1253", number = "7-9", volume = "83", doi = "10.1016/j.fusengdes.2008.05.031" }
Ilić, M., Kiss, B.,& Ihli, T.. (2008). Thermohydraulic experimental design for the European Helium-Cooled-Pebble-Bed Test Blanket Module. in Fusion Engineering and Design Elsevier Science Sa, Lausanne., 83(7-9), 1253-1257. https://doi.org/10.1016/j.fusengdes.2008.05.031
Ilić M, Kiss B, Ihli T. Thermohydraulic experimental design for the European Helium-Cooled-Pebble-Bed Test Blanket Module. in Fusion Engineering and Design. 2008;83(7-9):1253-1257. doi:10.1016/j.fusengdes.2008.05.031 .
Ilić, Milica, Kiss, Bela, Ihli, T., "Thermohydraulic experimental design for the European Helium-Cooled-Pebble-Bed Test Blanket Module" in Fusion Engineering and Design, 83, no. 7-9 (2008):1253-1257, https://doi.org/10.1016/j.fusengdes.2008.05.031 . .