Plasma exposure of a pre-damaged ITER-like plasma facing unit in the WEST tokamak: in-situ and post-mortem measurements. (March 2023)
- Record Type:
- Journal Article
- Title:
- Plasma exposure of a pre-damaged ITER-like plasma facing unit in the WEST tokamak: in-situ and post-mortem measurements. (March 2023)
- Main Title:
- Plasma exposure of a pre-damaged ITER-like plasma facing unit in the WEST tokamak: in-situ and post-mortem measurements
- Authors:
- Corre, Yann
Loewenhoff, Torsten
Richou, Marianne
Brezinsek, Sebastijan
Coenen, Jan
Dejarnac, Renaud
Diez, Mathilde
Fedorczak, Nicolas
Firdaouss, Mehdi
Gaspar, Jonathan
Grosjean, Alex
Gunn, James-Paul
Loarer, Thierry
Martin, Céline
Pintsuk, Gerald
Reilhac, Pierre
Tichit, Quentin
Tsitrone, Emmanuelle
Wirtz, Marius
WEST team, the - Abstract:
- Highlights: Infrared quantitative thermography. Damaged PFC. ITER like tungsten PFC. heat transfer modelling. Abstract: The consequences of tungsten (W) cracking on divertor lifetime and plasma operation are high priority issues for ITER. One actively cooled ITER-like plasma facing unit (PFU) has been pre-damaged in a High Heat Flux (HHF) facility before its installation in WEST in order to assess the damage evolution after tokamak plasma exposure. The resulting pre-damage exhibits micrometer-size crack network and high roughness on the tungsten monoblock (MB) top surface. A total of 10 MBs, equally distributed on the low and high field sides of the lower divertor, have been pre-damaged among the 35 radially aligned MBs characteristic of the WEST PFU. Subsequent plasma exposure was carried out, from the first breakdown achieved in WEST (in 2017) until the removal of the damaged PFU three years later (2020). On top of the whole WEST plasma exposure (covering C1-C4 experimental campaigns), a dedicated experiment has also been performed in the frame of the EU work program to maximize the power and energy loads on one of the damaged MBs featuring a "crack network" pattern. The MB top surface, including both "crack network" damage and "healthy" (undamaged) areas, was monitored with a high spatial resolution IR camera to detect any potential evolution of the damage pulse after pulse. This paper describes the full plasma exposure achieved in the WEST tokamak (including large numberHighlights: Infrared quantitative thermography. Damaged PFC. ITER like tungsten PFC. heat transfer modelling. Abstract: The consequences of tungsten (W) cracking on divertor lifetime and plasma operation are high priority issues for ITER. One actively cooled ITER-like plasma facing unit (PFU) has been pre-damaged in a High Heat Flux (HHF) facility before its installation in WEST in order to assess the damage evolution after tokamak plasma exposure. The resulting pre-damage exhibits micrometer-size crack network and high roughness on the tungsten monoblock (MB) top surface. A total of 10 MBs, equally distributed on the low and high field sides of the lower divertor, have been pre-damaged among the 35 radially aligned MBs characteristic of the WEST PFU. Subsequent plasma exposure was carried out, from the first breakdown achieved in WEST (in 2017) until the removal of the damaged PFU three years later (2020). On top of the whole WEST plasma exposure (covering C1-C4 experimental campaigns), a dedicated experiment has also been performed in the frame of the EU work program to maximize the power and energy loads on one of the damaged MBs featuring a "crack network" pattern. The MB top surface, including both "crack network" damage and "healthy" (undamaged) areas, was monitored with a high spatial resolution IR camera to detect any potential evolution of the damage pulse after pulse. This paper describes the full plasma exposure achieved in the WEST tokamak (including large number of steady-state and transient heat loading cycles), the dedicated "damaged PFU exposure" experiment together with the experimental results (heat loading on the damaged MBs). Post-mortem measurement reveals significant broadening of the cracks and new cracks in the electron beam loaded area only. … (more)
- Is Part Of:
- Nuclear materials and energy. Volume 34(2023)
- Journal:
- Nuclear materials and energy
- Issue:
- Volume 34(2023)
- Issue Display:
- Volume 34, Issue 2023 (2023)
- Year:
- 2023
- Volume:
- 34
- Issue:
- 2023
- Issue Sort Value:
- 2023-0034-2023-0000
- Page Start:
- Page End:
- Publication Date:
- 2023-03
- Subjects:
- Damaged PFC -- ITER like tungsten PFC -- Heat load -- IR thermography -- Heat transfer modelling
Nuclear energy -- Periodicals
Nuclear fuels -- Periodicals
Nuclear reactors -- Materials -- Periodicals
Radioactive substances -- Periodicals
621.4833 - Journal URLs:
- http://www.sciencedirect.com/science/journal/23521791 ↗
http://www.sciencedirect.com/ ↗ - DOI:
- 10.1016/j.nme.2023.101366 ↗
- Languages:
- English
- ISSNs:
- 2352-1791
- Deposit Type:
- Legaldeposit
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- Available online (eLD content is only available in our Reading Rooms) ↗
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- British Library DSC - BLDSS-3PM
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