Abstract
The focus has been put on D-doped Be-O, Be-W, Be-C-O (in the case of JET-ILW comparison) coatings with different surface morphologies in the nanoscale and thicknesses ranging from about 0.1 um to some 15 um. The relative D content of the samples can routinely be increased to 5-10 at.%, and in some coating types even 40 at.% has been reached. This is a good starting point to fabricate co-deposits with seeding gases and/or helium in the future. The Be-O-C-D coatings most closely resembling the JET-ILW co-deposits (O and C content 5-10 at.%, D content ~5 at.%, thickness ~15 um) show very similar release behavior of D as real JET samples, indicating that the laboratory samples well mimic the structure of co-deposits in fusion reactors.
The surface analyses have revealed that increasing the O content from a few to 50 at.% in otherwise identical samples lowers the amount of D that can be retained, by up to a factor of 10. Implantation with D+ ions results in similar retention behavior, though with more peaked D profiles, than direct doping during the deposition phase. The data also indicate that more D can accumulate in the sample if the thickness of the coating is increased, the surface becomes more modified and rough, or, in the case of mixed Be-W deposits, the relative Be fraction increases.
[1] K. Heinola et al., Experience on divertor fuel retention after two ITER-Like Wall campaigns, Phys. Scr. (accepted).
| Original language | English |
|---|---|
| Title of host publication | 23rd PSI Conference Princeton USA |
| Subtitle of host publication | Book of Abstracts |
| Publisher | Princeton University |
| Number of pages | 1 |
| Publication status | Published - Jun 2018 |
| MoE publication type | Not Eligible |
| Event | 23rd International Conference on Plasma Surface Interactions in Controlled Fusion Devices - Princeton University, Princeton, United States Duration: 17 Jun 2018 → 22 Jun 2018 https://psi2018.princeton.edu/ |
Conference
| Conference | 23rd International Conference on Plasma Surface Interactions in Controlled Fusion Devices |
|---|---|
| Abbreviated title | PSI-23 |
| Country | United States |
| City | Princeton |
| Period | 17/06/18 → 22/06/18 |
| Internet address |
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Production of ITER-relevant Be-containing laboratory samples for fuel retention investigations. / Hakola, Antti (Corresponding author); Heinola, Kalle; Likonen, Jari; Lungu, Cristian; Porosnicu, Corneliu; Alves, E; Mateus, R.; Radović, Iva Bogdanović; Siketić, Z.; Nemanic, V.
23rd PSI Conference Princeton USA: Book of Abstracts. Princeton University, 2018. 378.Research output: Chapter in Book/Report/Conference proceeding › Conference abstract in proceedings › Scientific
TY - CHAP
T1 - Production of ITER-relevant Be-containing laboratory samples for fuel retention investigations
AU - Hakola, Antti
AU - Heinola, Kalle
AU - Likonen, Jari
AU - Lungu, Cristian
AU - Porosnicu, Corneliu
AU - Alves, E
AU - Mateus, R.
AU - Radović, Iva Bogdanović
AU - Siketić, Z.
AU - Nemanic, V.
PY - 2018/6
Y1 - 2018/6
N2 - Since 2014, a large project has been running under the EUROfusion Consortium to produce ITER-relevant test samples for fuel-retention studies. The strategy is to deposit mixed, Be-containing coatings at the National Institute for Laser, Plasma and Radiation Physics in Romania and distribute the samples for analyses and/or ion-implantation in partner laboratories. The composition, thickness, and surface structure of the deposits have been varied to study their influence on the efficiency of D retention and to make predictions for ITER. For benchmarking purposes, samples resembling the co-deposited layers on the inner divertor of JET during its ITER-Like Wall (ILW) campaigns [1] have also been produced. The properties of the samples have been determined using a variety of surface-analysis tools including Rutherford Backscattering Spectroscopy (RBS), Nuclear Reaction Analysis (NRA), Time-of-flight Elastic Recoil Detection Analysis (TOF-ERDA), Secondary Ion Mass Spectrometry (SIMS), Thermal Desoprtion Spectroscopy (TDS), and Laser-Induced Breakdown Spectroscopy (LIBS). The focus has been put on D-doped Be-O, Be-W, Be-C-O (in the case of JET-ILW comparison) coatings with different surface morphologies in the nanoscale and thicknesses ranging from about 0.1 um to some 15 um. The relative D content of the samples can routinely be increased to 5-10 at.%, and in some coating types even 40 at.% has been reached. This is a good starting point to fabricate co-deposits with seeding gases and/or helium in the future. The Be-O-C-D coatings most closely resembling the JET-ILW co-deposits (O and C content 5-10 at.%, D content ~5 at.%, thickness ~15 um) show very similar release behavior of D as real JET samples, indicating that the laboratory samples well mimic the structure of co-deposits in fusion reactors.The surface analyses have revealed that increasing the O content from a few to 50 at.% in otherwise identical samples lowers the amount of D that can be retained, by up to a factor of 10. Implantation with D+ ions results in similar retention behavior, though with more peaked D profiles, than direct doping during the deposition phase. The data also indicate that more D can accumulate in the sample if the thickness of the coating is increased, the surface becomes more modified and rough, or, in the case of mixed Be-W deposits, the relative Be fraction increases.[1] K. Heinola et al., Experience on divertor fuel retention after two ITER-Like Wall campaigns, Phys. Scr. (accepted).
AB - Since 2014, a large project has been running under the EUROfusion Consortium to produce ITER-relevant test samples for fuel-retention studies. The strategy is to deposit mixed, Be-containing coatings at the National Institute for Laser, Plasma and Radiation Physics in Romania and distribute the samples for analyses and/or ion-implantation in partner laboratories. The composition, thickness, and surface structure of the deposits have been varied to study their influence on the efficiency of D retention and to make predictions for ITER. For benchmarking purposes, samples resembling the co-deposited layers on the inner divertor of JET during its ITER-Like Wall (ILW) campaigns [1] have also been produced. The properties of the samples have been determined using a variety of surface-analysis tools including Rutherford Backscattering Spectroscopy (RBS), Nuclear Reaction Analysis (NRA), Time-of-flight Elastic Recoil Detection Analysis (TOF-ERDA), Secondary Ion Mass Spectrometry (SIMS), Thermal Desoprtion Spectroscopy (TDS), and Laser-Induced Breakdown Spectroscopy (LIBS). The focus has been put on D-doped Be-O, Be-W, Be-C-O (in the case of JET-ILW comparison) coatings with different surface morphologies in the nanoscale and thicknesses ranging from about 0.1 um to some 15 um. The relative D content of the samples can routinely be increased to 5-10 at.%, and in some coating types even 40 at.% has been reached. This is a good starting point to fabricate co-deposits with seeding gases and/or helium in the future. The Be-O-C-D coatings most closely resembling the JET-ILW co-deposits (O and C content 5-10 at.%, D content ~5 at.%, thickness ~15 um) show very similar release behavior of D as real JET samples, indicating that the laboratory samples well mimic the structure of co-deposits in fusion reactors.The surface analyses have revealed that increasing the O content from a few to 50 at.% in otherwise identical samples lowers the amount of D that can be retained, by up to a factor of 10. Implantation with D+ ions results in similar retention behavior, though with more peaked D profiles, than direct doping during the deposition phase. The data also indicate that more D can accumulate in the sample if the thickness of the coating is increased, the surface becomes more modified and rough, or, in the case of mixed Be-W deposits, the relative Be fraction increases.[1] K. Heinola et al., Experience on divertor fuel retention after two ITER-Like Wall campaigns, Phys. Scr. (accepted).
M3 - Conference abstract in proceedings
BT - 23rd PSI Conference Princeton USA
PB - Princeton University
ER -