LIBS for tokamak plasma facing components characterisation: Perspectives on in situ tritium cartography
LIBS for tokamak plasma facing components characterisation: Perspectives on in situ tritium cartography
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DOI：
10.1016/j.nima.2012.12.042
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发表时间：
2013-08
影响因子：
1.4
通讯作者：
A. Semerok;C. Grisolia
中科院分区：
文献类型：
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作者：
A. Semerok;C. Grisolia
使用来自欧洲托卡马克（法国 CEA Cadarache 的 TORE SUPRA 和德国尤利希的 TEXTOR）的面向等离子体组件 (PFC) 进行原位 LIBS 远程测量的可行性已在实验室中使用 Q 开关纳秒 Nd-YAG 激光器进行了研究。确定了 LIBS 的特定属性和最佳参数，以进行深入的 PFC 表征。 LIBS 方法在英国联合欧洲环面 (JET) 上使用 EDGE LIDAR 激光系统（红宝石激光，3J，波长 690nm，脉冲持续时间 300ps，强度高达 70GW/cm2）进行了原位测试。利用优化的LIBS和检测系统，在400-600nm光谱范围内观察并鉴定了等离子体中H、CII、CrI和BeII的几条分析谱线。 LIBS 深度制图与所分析瓷砖的表面特性一致，从而证实了原位 LIBS 的可行性。讨论了更准确地提供氚浓度测量所需的进一步 LIBS 技术改进。
Feasibility of in situ LIBS remote measurements with the plasma facing components (PFCs) from the European tokamaks (TORE SUPRA, CEA Cadarache, France and TEXTOR, Julich, Germany) has been studied in laboratory using Q-switched nanosecond Nd–YAG lasers. LIBS particular properties and optimal parameters were determined for in-depth PFCs characterisation. The LIBS method was in situ tested on the Joint European Torus (JET) in the UK with the EDGE LIDAR Laser System (Ruby laser, 3J, 690nm wavelength, 300ps pulse duration, intensity up to 70GW/cm2). Several analytical spectral lines of H, CII, CrI, and BeII in plasma were observed and identified in 400–600nm spectral range with the optimised LIBS and detection system. The LIBS in-depth cartography is in agreement with the surface properties of the tile under analysis, thus confirming feasibility of in situ LIBS. Further LIBS technique improvements required to provide tritium concentration measurements more accurately are discussed.