Overview of tritium retention in divertor tiles and dust particles from the JET tokamak with the ITER-like wall

被引：0
|
作者：
Torikai, Y. [1 ]
Kikuchi, G. [1 ]
Owada, A. [1 ]
Masuzaki, S. [2 ]
Otsuka, T. [3 ]
Ashikawa, N. [2 ,4 ]
Yajima, M. [2 ]
Tokitani, M. [2 ]
Oya, Y. [5 ]
Lee, S. E. [6 ]
Hatano, Y. [6 ]
Asakura, N. [7 ]
Hayashi, T. [8 ]
Oyaidzu, M. [8 ]
Likonen, J. [9 ]
Widdowson, A. [10 ]
Rubel, M. [11 ,12 ]
机构：
[1] Ibaraki Univ, Grad Sch Sci & Engn, Mito, Japan
[2] Natl Inst Fusion Sci, Toki, Japan
[3] Kindai Univ, Higashi, Osaka, Japan
[4] SOKENDAI, Toki, Japan
[5] Shizuoka Univ, Shizuoka, Japan
[6] Toyama Univ, Hydrogen Isotope Res Ctr, Toyama 9308555, Japan
[7] Natl Inst Quantum & Radiol Sci & Technol, Naka, Japan
[8] Natl Inst Quantum & Radiol Sci & Technol, Rokkasho 0393212, Japan
[9] VTT Tech Res Ctr Finland, Otakaari 3J, Lappeenranta 02150, Finland
[10] United Kingdom Atom Energy Author, Culham Ctr Fusion Energy, Culham Sci Ctr, Abingdon OX14 3DB, England
[11] KTH Royal Inst Technol, S-10044 Stockholm, Sweden
[12] Uppsala Univ, Box 516, S-75120 Uppsala, Sweden
来源：
NUCLEAR FUSION | 2024年 / 64卷 / 01期
基金：
英国工程与自然科学研究理事会; 瑞典研究理事会;
关键词：
JET; ITER like wall; tritium; divertor; dust; DEUTERIUM; PENETRATION;
D O I：
10.1088/1741-4326/ad0c08
中图分类号：
O35 [流体力学]; O53 [等离子体物理学];
学科分类号：
070204 ; 080103 ; 080704 ;
摘要：
Divertor tiles after Joint European Torus-ITER like wall (JET-ILW) campaigns and dust collected after JET-C and JET-ILW operation were examined by a set of complementary techniques (full combustion and radiography) to determine the total, specific and areal tritium activities, poloidal tritium distribution in the divertor and the presence of that isotope in individual dust particles. In the divertor tiles, the majority of tritium is detected in the surface region and, the areal activities in the ILW divertor are in the 0.5-12 kBq cm-2 range. The activity in the ILW dust is associated mainly with the presence of carbon particles being a legacy from the JET-C operation. The total tritium activities show significant differences between the JET operation with ILW and the earlier phase with the carbon wall (JET-C) indicating that tritium retention has been significantly decreased in the operation with ILW.
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页数：10
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