Search results
- 1.0579108 - ÚFP 2024 RIV NL eng J - Journal Article
Dorow-Gerspach, D. - Bram, M. - Ganesh, V. - Matějíček, Jiří - Pintsuk, G. - Vilémová, Monika - Wirtz, M. - Linsmeier, Ch.
Benchmarking by high heat flux testing of W-steel joining technologies.
Nuclear Materials and Energy. Roč. 37, December (2023), č. článku 101508. E-ISSN 2352-1791
EU Projects: European Commission(BE) 101052200
Institutional support: RVO:61389021
Keywords : Atmospheric plasma spraying * Ductile interlayer * Functionally graded material * High heat flux benchmark test * Spark plasma sintering * W/steel joints
OECD category: Materials engineering
Impact factor: 2.3, year: 2023
Method of publishing: Open access
https://www.sciencedirect.com/science/article/pii/S2352179123001473?via%3Dihub
Permanent Link: https://hdl.handle.net/11104/0347975 - 2.0579095 - ÚFP 2024 RIV NL eng J - Journal Article
Smolík, V. - Gleitz, M. - Zácha, P. - Entler, Slavomír
Commissioning of the inductive heater for hypervapotron testing.
Fusion Engineering and Design. Roč. 194, September (2023), č. článku 113928. ISSN 0920-3796. E-ISSN 1873-7196
R&D Projects: GA MŠMT EF16_019/0000778
Grant - others:AV ČR(CZ) StrategieAV21/27
Program: StrategieAV
Institutional support: RVO:61389021
Keywords : ANSYS fluent * ANSYS maxwell * High heat flux cooling * Hypervapotron
OECD category: Nuclear related engineering
Impact factor: 1.9, year: 2023
Method of publishing: Limited access
https://www.sciencedirect.com/science/article/pii/S0920379623005100?via%3Dihub
Permanent Link: https://hdl.handle.net/11104/0347960 - 3.0573323 - ÚFP 2024 RIV CH eng J - Journal Article
Ganesh, V. - Dorow-Gerspach, D. - Bram, M. - Linsmeier, Ch. - Matějíček, Jiří - Vilémová, Monika
High Heat Flux Testing of Graded W-Steel Joining Concepts for the First Wall.
Energies. Roč. 16, č. 9 (2023), č. článku 3664. ISSN 1996-1073. E-ISSN 1996-1073
Institutional support: RVO:61389021
Keywords : atmospheric plasma spraying (APS) * functionally graded material (FGM) * high heat flux (HHF) * spark plasma sintering (SPS) * W-steel
OECD category: Materials engineering
Impact factor: 3, year: 2023
Method of publishing: Open access
https://www.mdpi.com/1996-1073/16/9/3664
Permanent Link: https://hdl.handle.net/11104/0343787 - 4.0519145 - ÚFP 2020 RIV KR eng J - Journal Article
Zacha, P. - Entler, Slavomír
High heat flux limits of the fusion reactor water-cooled first wall.
Nuclear Engineering and Technology. Roč. 51, č. 5 (2019), s. 1251-1260. ISSN 1738-5733. E-ISSN 1738-5733
Institutional support: RVO:61389021
Keywords : friction factor characteristics * helical screw-tape * turbulent-flow * enhancement * design * High heat flux * Thermal performance factors * Turbulator promoters * First wall * Cooling * cfd
OECD category: Nuclear physics
Impact factor: 1.846, year: 2019
Method of publishing: Limited access
https://www.sciencedirect.com/science/article/pii/S1738573318304182?via%3Dihub
Permanent Link: http://hdl.handle.net/11104/0304179 - 5.0480958 - ÚFP 2018 RIV CH eng J - Journal Article
Prokůpek, J. - Samec, K. - Jílek, R. - Gavila, P. - Neufuss, S. - Entler, Slavomír
HELCZA-High heat flux test facility for testing ITER EU first wall components.
Fusion Engineering and Design. Roč. 124, November (2017), s. 187-190. ISSN 0920-3796. E-ISSN 1873-7196.
[SOFT 2016: Symposium on Fusion Technology /29./. Prague, 05.09.2016-09.09.2016]
Institutional support: RVO:61389021
Keywords : HELCZA * High heat flux * Electron beam testing * Test facility * Plasma facing components * First wall * Divertora
OECD category: Nuclear related engineering
Impact factor: 1.437, year: 2017
www.sciencedirect.com/science/article/pii/S0920379617302818
Permanent Link: http://hdl.handle.net/11104/0276601 - 6.0452058 - ÚFP 2016 CZ eng J - Journal Article
Domalapally, P.K. - Entler, Slavomír
Comparison of cooling schemes for high heat flux components cooling in fusion reactors.
Acta Polytechnica. Roč. 55, č. 2 (2015), s. 86-95. ISSN 1210-2709. E-ISSN 1805-2363
Keywords : Critical heat flux * High heat flux components * Helium cooling * Water cooling
Subject RIV: JF - Nuclear Energetics
http://ojs.cvut.cz/ojs/index.php/ap
Permanent Link: http://hdl.handle.net/11104/0253068