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Luo C, Xu L, Zong L, Shen H, Wei S. Research status of tungsten-based plasma-facing materials: A review. FUSION ENGINEERING AND DESIGN 2023. [DOI: 10.1016/j.fusengdes.2023.113487] [Citation(s) in RCA: 0] [Impact Index Per Article: 0] [Reference Citation Analysis] [Track Full Text] [Subscribe] [Scholar Register] [Indexed: 02/08/2023]
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2
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Li Y, Zhou T, Jiang S, Qian X. Hot Spot Cause Analysis and Shaping Optimization Design of the Monoblock Divertor Target Plate in EAST. FUSION SCIENCE AND TECHNOLOGY 2023. [DOI: 10.1080/15361055.2023.2169026] [Citation(s) in RCA: 0] [Impact Index Per Article: 0] [Reference Citation Analysis] [Track Full Text] [Subscribe] [Scholar Register] [Indexed: 03/18/2023]
Affiliation(s)
- Yilong Li
- Hebei University of Science and Technology, Shijiazhuang 050018, China
| | - Tong Zhou
- Chinese Academy of Sciences, Hefei Institutes of Physical Science, Institute of Plasma Physics, Hefei 230031, China
| | - Shili Jiang
- Chinese Academy of Sciences, Hefei Institutes of Physical Science, High Magnetic Field Laboratory, Hefei 230031, China
| | - Xinxing Qian
- Chinese Academy of Sciences, Hefei Institutes of Physical Science, High Magnetic Field Laboratory, Hefei 230031, China
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3
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Overview of plasma-tungsten surfaces interactions on the divertor test sector in WEST during the C3 and C4 campaigns. NUCLEAR MATERIALS AND ENERGY 2023. [DOI: 10.1016/j.nme.2023.101399] [Citation(s) in RCA: 0] [Impact Index Per Article: 0] [Reference Citation Analysis] [Track Full Text] [Subscribe] [Scholar Register] [Indexed: 02/27/2023]
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4
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Second plasma exposure of a pre-damaged ITER-like Plasma Facing Unit in the WEST tokamak: in-situ and post-mortem measurements. NUCLEAR MATERIALS AND ENERGY 2023. [DOI: 10.1016/j.nme.2023.101366] [Citation(s) in RCA: 0] [Impact Index Per Article: 0] [Reference Citation Analysis] [Track Full Text] [Subscribe] [Scholar Register] [Indexed: 01/22/2023]
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5
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Gaspar J, Rigollet F, Ehret N, Anquetin Y, Bernard E, Corre Y, Diez M, Firdaouss M, Houry M, Loarer T, Martin C, Missirlian M, Moreau P, Pocheau C, Reihlac P, Richou M, Tsitrone E. Emissivity measurement of the ITER-like plasma facing components of the WEST phase 2: pre-exposure measurements and first WEST exposure. NUCLEAR MATERIALS AND ENERGY 2022. [DOI: 10.1016/j.nme.2022.101305] [Citation(s) in RCA: 0] [Impact Index Per Article: 0] [Reference Citation Analysis] [Track Full Text] [Subscribe] [Scholar Register] [Indexed: 11/16/2022]
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6
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Ramaniraka M, Richou M, Vignal N, Addab Y, Missirlian M. Reception tests of the WEST PFUs using ultrasonic testing and infrared thermography. NUCLEAR MATERIALS AND ENERGY 2022. [DOI: 10.1016/j.nme.2022.101210] [Citation(s) in RCA: 0] [Impact Index Per Article: 0] [Reference Citation Analysis] [Track Full Text] [Subscribe] [Scholar Register] [Indexed: 11/30/2022]
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7
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Pintsuk G, Missirlian M, Luo GN, Li Q, Wang W, Guilhem D, Bucalossi J. High heat flux testing of newly developed tungsten components for WEST. FUSION ENGINEERING AND DESIGN 2021. [DOI: 10.1016/j.fusengdes.2021.112835] [Citation(s) in RCA: 3] [Impact Index Per Article: 1.0] [Reference Citation Analysis] [Track Full Text] [Subscribe] [Scholar Register] [Indexed: 11/28/2022]
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8
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Barbui T, Chellai O, Delgado-Aparicio L, Ellis R, Hill K, Stratton B, Wallace J, Wisniewski J, Cantone B, Dumont R, Fedorczak N, Hatchressian J, Lotte P, Malard P. Design and engineering challenges of a multi-energy hard x-ray camera for long-pulse profile measurements at WEST tokamak. FUSION ENGINEERING AND DESIGN 2021. [DOI: 10.1016/j.fusengdes.2021.112957] [Citation(s) in RCA: 1] [Impact Index Per Article: 0.3] [Reference Citation Analysis] [Track Full Text] [Subscribe] [Scholar Register] [Indexed: 11/16/2022]
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9
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Corre Y, Chanet N, Cotillard R, Gaspar J, Laffont G, Pocheau C, Caulier G, Destouches C, Gardarein JL, Firdaouss M, Houry M, Missirlian M, Roussel N, Santraine B. First temperature database achieved with Fiber Bragg Grating sensors in uncooled plasma facing components of the WEST lower divertor. FUSION ENGINEERING AND DESIGN 2021. [DOI: 10.1016/j.fusengdes.2021.112528] [Citation(s) in RCA: 0] [Impact Index Per Article: 0] [Reference Citation Analysis] [Track Full Text] [Subscribe] [Scholar Register] [Indexed: 10/21/2022]
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Grosjean A, Aumeunier M, Corre Y, Firdaouss M, Gaspar J, Gerardin J, Gunn J, Courtois X, Dejarnac R, Diez M, Dubus L, Houry M, Pocheau C, Tsitrone E. Interpretation of temperature distribution observed on W-ITER-like PFUs in WEST monitored with a very-high-resolution IR system. FUSION ENGINEERING AND DESIGN 2021. [DOI: 10.1016/j.fusengdes.2021.112387] [Citation(s) in RCA: 2] [Impact Index Per Article: 0.7] [Reference Citation Analysis] [Track Full Text] [Subscribe] [Scholar Register] [Indexed: 11/16/2022]
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Very high-resolution infrared imagery of misaligned tungsten monoblock edge heating in the WEST tokamak. NUCLEAR MATERIALS AND ENERGY 2021. [DOI: 10.1016/j.nme.2021.100910] [Citation(s) in RCA: 3] [Impact Index Per Article: 1.0] [Reference Citation Analysis] [Track Full Text] [Subscribe] [Scholar Register] [Indexed: 11/22/2022]
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12
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Design and integration of femtosecond Fiber Bragg gratings temperature probes inside actively cooled ITER-like plasma-facing components. FUSION ENGINEERING AND DESIGN 2021. [DOI: 10.1016/j.fusengdes.2021.112376] [Citation(s) in RCA: 2] [Impact Index Per Article: 0.7] [Reference Citation Analysis] [Track Full Text] [Subscribe] [Scholar Register] [Indexed: 11/22/2022]
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Wang Y, Yan Q. Preparation of hot-rolled potassium doped tungsten (KW) thick plate and performance of KW-Cu monoblock mock-ups under high heat flux testing. NUCLEAR MATERIALS AND ENERGY 2020. [DOI: 10.1016/j.nme.2020.100744] [Citation(s) in RCA: 2] [Impact Index Per Article: 0.5] [Reference Citation Analysis] [Track Full Text] [Subscribe] [Scholar Register] [Indexed: 10/24/2022]
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14
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Peng X, Liu P, Lu K, Qin S, Mao X, Qian X. Design optimization of plasma facing unit fixation distribution for CFETR divertor. FUSION ENGINEERING AND DESIGN 2020. [DOI: 10.1016/j.fusengdes.2019.111434] [Citation(s) in RCA: 0] [Impact Index Per Article: 0] [Reference Citation Analysis] [Track Full Text] [Subscribe] [Scholar Register] [Indexed: 10/25/2022]
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Coenen J, Mao Y, Sistla S, Müller A, Pintsuk G, Wirtz M, Riesch J, Hoeschen T, Terra A, You JH, Greuner H, Kreter A, Broeckmann C, Neu R, Linsmeier C. Materials development for new high heat-flux component mock-ups for DEMO. FUSION ENGINEERING AND DESIGN 2019. [DOI: 10.1016/j.fusengdes.2019.02.098] [Citation(s) in RCA: 14] [Impact Index Per Article: 2.8] [Reference Citation Analysis] [Track Full Text] [Subscribe] [Scholar Register] [Indexed: 11/28/2022]
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Gaspar J, Corre Y, Firdaouss M, Gardarein J, Gerardin J, Gunn J, Houry M, Laffont G, Loarer T, Missirlian M, Morales J, Moreau P, Pocheau C, Tsitrone E. First heat flux estimation in the lower divertor of WEST with embedded thermal measurements. FUSION ENGINEERING AND DESIGN 2019. [DOI: 10.1016/j.fusengdes.2019.01.074] [Citation(s) in RCA: 17] [Impact Index Per Article: 3.4] [Reference Citation Analysis] [Track Full Text] [Subscribe] [Scholar Register] [Indexed: 11/29/2022]
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Missirlian M, Pintsuk G, Luo GN, Li Q, Wang W, Durif A, Batal T, Richou M, Bucalossi J. Qualification and post-mortem investigation of actively cooled tungsten flat-tile mock-ups for WEST divertor. FUSION ENGINEERING AND DESIGN 2018. [DOI: 10.1016/j.fusengdes.2018.02.063] [Citation(s) in RCA: 4] [Impact Index Per Article: 0.7] [Reference Citation Analysis] [Track Full Text] [Subscribe] [Scholar Register] [Indexed: 11/27/2022]
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18
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Virtual Reality: Lessons learned from WEST design and perspectives for nuclear environment. FUSION ENGINEERING AND DESIGN 2018. [DOI: 10.1016/j.fusengdes.2018.05.004] [Citation(s) in RCA: 6] [Impact Index Per Article: 1.0] [Reference Citation Analysis] [Track Full Text] [Subscribe] [Scholar Register] [Indexed: 11/19/2022]
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19
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Corre Y, Laffont G, Pocheau C, Cotillard R, Gaspar J, Roussel N, Firdaouss M, Gardarein JL, Guilhem D, Missirlian M. Integration of fiber Bragg grating temperature sensors in plasma facing components of the WEST tokamak. THE REVIEW OF SCIENTIFIC INSTRUMENTS 2018; 89:063508. [PMID: 29960581 DOI: 10.1063/1.5024514] [Citation(s) in RCA: 15] [Impact Index Per Article: 2.5] [Reference Citation Analysis] [Abstract] [Track Full Text] [Subscribe] [Scholar Register] [Indexed: 06/08/2023]
Abstract
Plasma Facing Components (PFC) temperature measurement is mandatory to ensure safe high power and long pulse tokamak operation. IR thermography systems which are widely used in magnetic fusions devices become challenged with the choice of tungsten as a PFC material in the ITER tokamak, mainly due to emissivity uncertainties and reflection issues in a hot environment. Embedded temperature measurements are foreseen to cross-check the IR thermography measurements. Fiber Bragg grating sensors are potentially of great interest for this application because they are immune to electromagnetic interference and allow the measurement of a large number of temperature spots on a single fiber. Four optical fiber temperature sensing probes, each of them including 11 regenerated fiber Bragg gratings equally spaced by 12.5 mm (equivalent to one ITER-like tungsten monoblock), have been specifically designed and manufactured for the WEST project (W-tungsten Environment and Steady State Tokamak). The four probes are embedded in W-coated graphite components at two different distances from the surface, 3.5 mm and 7 mm, to cover a wide range of temperatures up to 900 °C. This paper addresses the design and integration issues and the qualification and performance assessment performed in the laboratory. It also shows the first measurements of this new diagnostic achieved in a tokamak environment during baking of the machine and during early diverted plasma exposure.
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Affiliation(s)
- Y Corre
- CEA, IRFM, F-13108 Saint-Paul-lez-Durance, France
| | - G Laffont
- CEA, LIST, Gif-sur-Yvette Cedex 91191, France
| | - C Pocheau
- CEA, IRFM, F-13108 Saint-Paul-lez-Durance, France
| | - R Cotillard
- CEA, LIST, Gif-sur-Yvette Cedex 91191, France
| | - J Gaspar
- CEA, IRFM, F-13108 Saint-Paul-lez-Durance, France
| | - N Roussel
- CEA, LIST, Gif-sur-Yvette Cedex 91191, France
| | - M Firdaouss
- CEA, IRFM, F-13108 Saint-Paul-lez-Durance, France
| | - J-L Gardarein
- Aix-Marseille Université, CNRS, IUSTI UMR 7343, 13013 Marseille, France
| | - D Guilhem
- CEA, IRFM, F-13108 Saint-Paul-lez-Durance, France
| | - M Missirlian
- CEA, IRFM, F-13108 Saint-Paul-lez-Durance, France
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Muller A, Ewert D, Galatanu A, Milwich M, Neu R, Pastor J, Siefken U, Tejado E, You J. Melt infiltrated tungsten–copper composites as advanced heat sink materials for plasma facing components of future nuclear fusion devices. FUSION ENGINEERING AND DESIGN 2017. [DOI: 10.1016/j.fusengdes.2017.01.042] [Citation(s) in RCA: 48] [Impact Index Per Article: 6.9] [Reference Citation Analysis] [Track Full Text] [Subscribe] [Scholar Register] [Indexed: 11/28/2022]
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21
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Greuner H, Böswirth B, Maier H, Hirai T, Panayotis S, Crescenzi F, Roccella S, Visca E, Missirlian M, Richou M. Potential approach of IR-analysis for high heat flux quality assessment of divertor tungsten monoblock components. FUSION ENGINEERING AND DESIGN 2017. [DOI: 10.1016/j.fusengdes.2017.02.092] [Citation(s) in RCA: 5] [Impact Index Per Article: 0.7] [Reference Citation Analysis] [Track Full Text] [Subscribe] [Scholar Register] [Indexed: 11/26/2022]
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22
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Surface heat flux estimation with embedded fiber Bragg gratings measurements: Numerical study. NUCLEAR MATERIALS AND ENERGY 2017. [DOI: 10.1016/j.nme.2016.10.015] [Citation(s) in RCA: 6] [Impact Index Per Article: 0.9] [Reference Citation Analysis] [Track Full Text] [Subscribe] [Scholar Register] [Indexed: 11/22/2022]
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Grigore E, Gherendi M, Hernandez C, Desgranges C, Firdaouss M. Tungsten coatings for application in WEST project. NUCLEAR MATERIALS AND ENERGY 2016. [DOI: 10.1016/j.nme.2016.09.003] [Citation(s) in RCA: 1] [Impact Index Per Article: 0.1] [Reference Citation Analysis] [Track Full Text] [Subscribe] [Scholar Register] [Indexed: 10/21/2022]
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Chen F, Tang X, Huang H, Li X, Wang Y, Huang C, Liu J, Li H, Chen D. Formation of He-Rich Layers Observed by Neutron Reflectometry in the He-Ion-Irradiated Cr/W Multilayers: Effects of Cr/W Interfaces on the He-Trapping Behavior. ACS APPLIED MATERIALS & INTERFACES 2016; 8:24300-24305. [PMID: 27589251 DOI: 10.1021/acsami.6b07419] [Citation(s) in RCA: 1] [Impact Index Per Article: 0.1] [Reference Citation Analysis] [Abstract] [Key Words] [Track Full Text] [Subscribe] [Scholar Register] [Indexed: 06/06/2023]
Abstract
Cr/W multilayer nanocomposites were presented in the paper as potential candidate materials for the plasma facing components in fusion reactors. We used neutron reflectometry to measure the depth profile of helium in the multienergy He ions irradiated [Cr/W (50 nm)]3 multilayers. Results showed that He-rich layers with low neutron scattering potential energy form at the Cr/W interfaces, which is in great agreement with previous modeling results of other multilayers. This phenomenon provided a strong evidence for the He trapping effects of Cr/W interfaces and implied the possibility of using the Cr/W multilayer nanocomposites as great He-tolerant plasma facing materials.
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Affiliation(s)
- Feida Chen
- Department of Nuclear Science & Engineering, Nanjing University of Aeronautics and Astronautics , Nanjing 211106, China
| | - Xiaobin Tang
- Department of Nuclear Science & Engineering, Nanjing University of Aeronautics and Astronautics , Nanjing 211106, China
- Jiangsu Key Laboratory of Nuclear Energy Equipment Materials Engineering , Nanjing 211106, China
| | - Hai Huang
- Department of Nuclear Science & Engineering, Nanjing University of Aeronautics and Astronautics , Nanjing 211106, China
| | - Xinxi Li
- Institute of Nuclear Physics and Chemistry, China Academy of Engineering Physics , Mianyang 621900, China
| | - Yan Wang
- Institute of Nuclear Physics and Chemistry, China Academy of Engineering Physics , Mianyang 621900, China
| | - Chaoqiang Huang
- Institute of Nuclear Physics and Chemistry, China Academy of Engineering Physics , Mianyang 621900, China
| | - Jian Liu
- Department of Nuclear Science & Engineering, Nanjing University of Aeronautics and Astronautics , Nanjing 211106, China
| | - Huan Li
- Department of Nuclear Science & Engineering, Nanjing University of Aeronautics and Astronautics , Nanjing 211106, China
| | - Da Chen
- Department of Nuclear Science & Engineering, Nanjing University of Aeronautics and Astronautics , Nanjing 211106, China
- Jiangsu Key Laboratory of Nuclear Energy Equipment Materials Engineering , Nanjing 211106, China
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Plasma facing components integration studies for the WEST divertor. FUSION ENGINEERING AND DESIGN 2015. [DOI: 10.1016/j.fusengdes.2015.02.053] [Citation(s) in RCA: 7] [Impact Index Per Article: 0.8] [Reference Citation Analysis] [Track Full Text] [Subscribe] [Scholar Register] [Indexed: 11/22/2022]
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26
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Richou M, Missirlian M, Guilhem D, Lipa M, Languille P, Ferlay F, Gallay F, Greuner H, Hernandez C, Firdaouss M, Bucalossi J. Design and preliminary thermal validation of the WEST actively cooled upper divertor. FUSION ENGINEERING AND DESIGN 2015. [DOI: 10.1016/j.fusengdes.2014.12.017] [Citation(s) in RCA: 13] [Impact Index Per Article: 1.4] [Reference Citation Analysis] [Track Full Text] [Subscribe] [Scholar Register] [Indexed: 11/25/2022]
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27
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Thermal characterisation of ceramic/metal joining techniques for fusion applications using X-ray tomography. FUSION ENGINEERING AND DESIGN 2014. [DOI: 10.1016/j.fusengdes.2014.05.002] [Citation(s) in RCA: 11] [Impact Index Per Article: 1.1] [Reference Citation Analysis] [Track Full Text] [Subscribe] [Scholar Register] [Indexed: 11/21/2022]
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