A control-oriented model for monitoring of wall power flux densities on the DIII-D tokamak has been successfully implemented and validated experimentally. Future reactors will have to withstand severe steady state high heat flux loads on plasma-facing components (PFCs). Due to the difficulty of directly-measuring local heat fluxes on these components, monitoring and protection of PFCs during the plasma discharge can benefit from simplified physics-based real-time functional models to estimate and guide heat load control. As a first step into the development, a control-oriented model for monitoring of wall power flux densities and temperatures on DIII-D tokamak has been successfully implemented. The paper discusses the experimental demonstration and comparison of the 2D model-based wall heat flux algorithm on the DIII-D inner wall limiter (IWL) against infra-red (IR) camera heat flux measurements for limited plasma configurations. The paper also reports on the benchmarking of the field line tracing environment, SMITER, developed at ITER organization on DIII-D tokamak against experimental IR diagnostic data and the derivation of the component shaping weighting factors for the 2D model-based approach. Extension of the model-based approach for surface temperature estimation on the DIII-D IWL is also presented.

DIII-D托卡马克上壁式功率通量密度监控的面向控制模型已成功实施并通过实验验证。未来的反应堆将不得不承受面对等离子体的部件（PFC）的严重稳态高热通量负荷。由于难以直接测量这些组件上的局部热通量，因此，在等离子体放电过程中监视和保护PFC可以受益于简化的基于物理的实时功能模型，以估计和指导热负荷控制。作为开发的第一步，已成功实施了一种用于DIII-D托卡马克上壁功率通量密度和温度监控的面向控制模型。本文讨论了DIII-D内壁限制器（IWL）上基于二维模型的壁热通量算法与有限等离子体配置下的红外（IR）相机热通量测量的实验演示和比较。本文还报告了由ITER组织在DIII-D托卡马克上针对实验性IR诊断数据开发的基准线追踪环境SMITER的基准测试，以及基于2D模型的方法的分量成形权重因子的推导。还介绍了基于模型的方法在DIII-D IWL上的表面温度估计的扩展。由ITER组织在DIII-D托卡马克上针对实验性IR诊断数据以及基于2D模型的方法推导了零件成形权重因子而开发。还介绍了基于模型的方法在DIII-D IWL上的表面温度估计的扩展。由ITER组织在DIII-D托卡马克上针对实验性IR诊断数据以及基于2D模型的方法推导了零件成形权重因子得出。还介绍了基于模型的方法在DIII-D IWL上的表面温度估计的扩展。