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For: Aiello G, Aubert J, Jonquères N, Li Puma A, Morin A, Rampal G. Development of the Helium Cooled Lithium Lead blanket for DEMO. Fusion Engineering and Design 2014. [DOI: 10.1016/j.fusengdes.2013.12.036] [Citation(s) in RCA: 15] [Impact Index Per Article: 1.5] [Reference Citation Analysis] [What about the content of this article? (0)] [Track Full Text] [Subscribe] [Scholar Register] [Indexed: 10/25/2022]
Number Cited by Other Article(s)
1
Power conversion from spherical tokamak test reactor with helium-cooled and water-cooled blanket. FUSION ENGINEERING AND DESIGN 2022. [DOI: 10.1016/j.fusengdes.2022.113024] [Citation(s) in RCA: 0] [Impact Index Per Article: 0] [Reference Citation Analysis] [Track Full Text] [Subscribe] [Scholar Register] [Indexed: 11/24/2022]
2
Overview of the Mechanical Properties of Tungsten/Steel Brazed Joints for the DEMO Fusion Reactor. METALS 2021. [DOI: 10.3390/met11020209] [Citation(s) in RCA: 11] [Impact Index Per Article: 3.7] [Reference Citation Analysis] [Abstract] [Track Full Text] [Subscribe] [Scholar Register] [Indexed: 11/17/2022]
3
de les Valls EM, Cegielski A, Jaros M, Pérez-Ferragut M, Batet L, Sandeep T, Chaudhari V, Freixa J. Development of flow regime maps for lead lithium eutectic–helium flows. FUSION ENGINEERING AND DESIGN 2020. [DOI: 10.1016/j.fusengdes.2020.111691] [Citation(s) in RCA: 0] [Impact Index Per Article: 0] [Reference Citation Analysis] [Track Full Text] [Subscribe] [Scholar Register] [Indexed: 10/24/2022]
4
Neutronics conceptual research on a hybrid blanket of china fusion engineering test reactor. FUSION ENGINEERING AND DESIGN 2020. [DOI: 10.1016/j.fusengdes.2020.111715] [Citation(s) in RCA: 1] [Impact Index Per Article: 0.3] [Reference Citation Analysis] [Track Full Text] [Subscribe] [Scholar Register] [Indexed: 11/22/2022]
5
Aubert J, Aiello G, Arena P, Barrett T, Boccaccini LV, Bongiovì G, Boullon R, Cismondi F, Critescu I, Domalapally PK, Forest L, Jaboulay JC, Kiss B, Morin A, Peyraud J, Porempovics G, Utili M, Vála L. Status of the EU DEMO HCLL breeding blanket design development. FUSION ENGINEERING AND DESIGN 2018. [DOI: 10.1016/j.fusengdes.2018.04.133] [Citation(s) in RCA: 22] [Impact Index Per Article: 3.7] [Reference Citation Analysis] [Track Full Text] [Subscribe] [Scholar Register] [Indexed: 11/16/2022]
6
Numerical analyses for conceptual design of an irradiation PbLi capsule for testing of protective coatings for the European DEMO breeding blanket project. FUSION ENGINEERING AND DESIGN 2018. [DOI: 10.1016/j.fusengdes.2018.04.011] [Citation(s) in RCA: 6] [Impact Index Per Article: 1.0] [Reference Citation Analysis] [Track Full Text] [Subscribe] [Scholar Register] [Indexed: 11/20/2022]
7
Fusion Neutrons: Tritium Breeding and Impact on Wall Materials and Components of Diagnostic Systems. JOURNAL OF FUSION ENERGY 2018. [DOI: 10.1007/s10894-018-0182-1] [Citation(s) in RCA: 24] [Impact Index Per Article: 4.0] [Reference Citation Analysis] [Track Full Text] [Subscribe] [Scholar Register] [Indexed: 11/25/2022]
8
Jaboulay JC, Aiello G, Aubert J, Morin A, Troisne M. Nuclear analysis of the HCLL blanket for the European DEMO. FUSION ENGINEERING AND DESIGN 2017. [DOI: 10.1016/j.fusengdes.2017.01.050] [Citation(s) in RCA: 9] [Impact Index Per Article: 1.3] [Reference Citation Analysis] [Track Full Text] [Subscribe] [Scholar Register] [Indexed: 11/30/2022]
9
Thermal optimization of the Helium-Cooled Lithium Lead breeding zone layout design regarding TBR enhancement. FUSION ENGINEERING AND DESIGN 2017. [DOI: 10.1016/j.fusengdes.2017.03.086] [Citation(s) in RCA: 7] [Impact Index Per Article: 1.0] [Reference Citation Analysis] [Track Full Text] [Subscribe] [Scholar Register] [Indexed: 11/19/2022]
10
Tritium transport in HCLL and WCLL DEMO blankets. FUSION ENGINEERING AND DESIGN 2016. [DOI: 10.1016/j.fusengdes.2016.03.017] [Citation(s) in RCA: 13] [Impact Index Per Article: 1.6] [Reference Citation Analysis] [Track Full Text] [Subscribe] [Scholar Register] [Indexed: 11/20/2022]
11
Barrett TR, Ellwood G, Pérez G, Kovari M, Fursdon M, Domptail F, Kirk S, McIntosh S, Roberts S, Zheng S, Boccaccini L, You JH, Bachmann C, Reiser J, Rieth M, Visca E, Mazzone G, Arbeiter F, Domalapally P. Progress in the engineering design and assessment of the European DEMO first wall and divertor plasma facing components. FUSION ENGINEERING AND DESIGN 2016. [DOI: 10.1016/j.fusengdes.2016.01.052] [Citation(s) in RCA: 58] [Impact Index Per Article: 7.3] [Reference Citation Analysis] [Track Full Text] [Subscribe] [Scholar Register] [Indexed: 11/16/2022]
12
Theoretical studies of MHD flows in support to HCLL design activities. FUSION ENGINEERING AND DESIGN 2016. [DOI: 10.1016/j.fusengdes.2015.11.010] [Citation(s) in RCA: 8] [Impact Index Per Article: 1.0] [Reference Citation Analysis] [Track Full Text] [Subscribe] [Scholar Register] [Indexed: 11/20/2022]
13
Aubert J, Aiello G, Jaboulay JC, Kiss B, Morin A. Status on DEMO Helium Cooled Lithium Lead breeding blanket thermo-mechanical analyses. FUSION ENGINEERING AND DESIGN 2016. [DOI: 10.1016/j.fusengdes.2016.01.037] [Citation(s) in RCA: 10] [Impact Index Per Article: 1.3] [Reference Citation Analysis] [Track Full Text] [Subscribe] [Scholar Register] [Indexed: 11/25/2022]
14
Jaboulay JC, Aiello G, Aubert J, Villari R, Fischer U. Comparison over the nuclear analysis of the HCLL blanket for the European DEMO. FUSION ENGINEERING AND DESIGN 2016. [DOI: 10.1016/j.fusengdes.2016.02.097] [Citation(s) in RCA: 4] [Impact Index Per Article: 0.5] [Reference Citation Analysis] [Track Full Text] [Subscribe] [Scholar Register] [Indexed: 10/22/2022]
15
Li-Puma A, Jaboulay JC, Martin B. Development of the breeding blanket and shield model for the fusion power reactors system SYCOMORE. FUSION ENGINEERING AND DESIGN 2014. [DOI: 10.1016/j.fusengdes.2014.04.058] [Citation(s) in RCA: 5] [Impact Index Per Article: 0.5] [Reference Citation Analysis] [Track Full Text] [Subscribe] [Scholar Register] [Indexed: 10/25/2022]
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