WEST is a full W tokamak with an extensive set of diagnostics for heat load measurements especially in the lower divertor. It is composed by infrared thermography, thermal measurement with thermocouples and fibre Bragg grating embedded few mm below the surface and flush mounted Langmuir probes. A large database including different magnetic equilibrium and input power is investigated to compare the heat load pattern (location, amplitude of the peak and heat flux decay length) on the inner and outer strike point regions: from the first ohmic diverted plasma (obtained during the second experimental campaign C2 in 2018) up to the high power (8MW total injected) and high energy (up to 90 MJ injected energy in lower single null configuration) experiments performed in the last experimental campaign (C4 in 2019). Concerning the peak location, a good agreement (<1cm) is obtained between thermal inversions and flush-mounted LP measurements. The peak heat flux from the whole set of diagnostics is in good agreement and mainly in the 20% range, while the heat flux decay length reported on the target shows significant discrepancy between diagnostics and location in the machine (40% range). Despite such discrepancy, heat flux decay length at target is found to scale mainly with the magnetic flux expansion through the variation of the X-point height, as expected. The improved plasma performances achieved during C4 enabled to reach significant heat load in the divertor, up to 6MWm⁻² with 4MW of additional heating power showing the capability to reach the ITER relevant heat load (10MWm⁻² steady state) with about 7MW of additional power in L-mode discharge. The heat load distribution is clearly asymmetric with a 3/4 and 1/4 distribution on the outer and inner strike point region respectively for the parallel heat flux.

WEST 是一个完整的 W 托卡马克，具有用于热负荷测量的广泛诊断集，尤其是在下部偏滤器中。它由红外热成像、热电偶热测量和嵌入表面以下几毫米的光纤布拉格光栅和嵌入式朗缪尔探头组成。研究了一个包含不同磁平衡和输入功率的大型数据库，以比较内部和外部撞击点区域的热负荷模式（位置、峰值幅度和热通量衰减长度）：从第一个欧姆转向等离子体（在2018 年的第二个实验活动 C2）直到上一个实验活动（2019 年的 C4）中进行的高功率（8MW 总注入）和高能量（在较低的单空配置中注入能量高达 90 MJ）实验。关于峰的位置，热反转和嵌入式安装的 LP 测量之间获得了良好的一致性 (<1cm)。来自整套诊断的峰值热通量非常一致，主要在 20% 的范围内，而在目标上报告的热通量衰减长度显示诊断与机器中的位置（40% 范围）之间存在显着差异。尽管存在这种差异，但正如预期的那样，发现目标处的热通量衰减长度主要与通过 X 点高度变化的磁通量扩展成比例。在 C4 期间实现的改进的等离子体性能使偏滤器的热负荷达到了高达 6MWm 而在目标上报告的热通量衰减长度显示诊断和机器中的位置之间存在显着差异（40% 范围）。尽管存在这种差异，但发现目标处的热通量衰减长度主要与通过 X 点高度变化的磁通量扩展成比例，正如预期的那样。在 C4 期间实现的改进的等离子体性能能够在偏滤器中达到显着的热负荷，高达 6MWm 而在目标上报告的热通量衰减长度显示诊断和机器中的位置之间存在显着差异（40% 范围）。尽管存在这种差异，但发现目标处的热通量衰减长度主要与通过 X 点高度变化的磁通量扩展成比例，正如预期的那样。在 C4 期间实现的改进的等离子体性能使偏滤器的热负荷达到了高达 6MWm^-2具有 4MW 的附加加热功率，表明在 L 模式放电中具有约 7MW 的附加功率时能够达到 ITER 相关热负荷（10MWm ^-2稳态）。热负荷分布显然是不对称的，平行热通量的外部和内部撞击点区域分别为 3/4 和 1/4 分布。