This paper gives guidelines for assessing the structural integrity of plasma facing components (PFC)when irradiated to the levels expected in DEMO after two full power years. The paper is part II of a 3-part paper describing the EuroFusion DEMO Divertor group (WPDIV) Inelastic Analysis procedure (IAP), created to improve the assessment of PFCs, and specifically those constructed from tungsten armour cooled by CuCrZr heat sink (with Copper interlayer). The paper first provides a recap of the IAP methodology detailed in the part 1 paper and then presents a detailed review of the limited relevant irradiated materials data on material properties (thermal conductivity, swelling and stress-strain curves) and materials limit data (rupture-strain, fracture-toughness and fatigue strength). The data is used in an example structural integrity assessment estimate of an ITER-like divertor “monoblock” PFC (tungsten block with through CuCrZr pipe) when irradiated to ∼14dpa (CuCrZr) & ∼ 4dp (tungsten). The assessment uses IAP methodologies to determine the susceptibility of the design to failure by exhaustion-of-ductility, fast-fracture, fatigue and ratcheting in the CuCrZr pipe, exhaustion of ductility in the copper interlayer and brittle fracture in the tungsten armour. These methodologies ensure that contributions from changes in both material limit-levels and material properties are included. The paper documents the extrapolations required to extend the existing irradiated materials data to the expected dpa and temperature range. The assessment exposes significant shortfalls in the monoblock type design in coping with the drastic reduction in copper ductility and tungsten strength caused by irradiation. This illustrates that maintaining structural integrity when irradiated poses a far more stringent constraint on a PFC design than the un-irradiated condition, and as such should be given priority in future design studies. Although the prime aim of the paper is to present assessment methodologies, it also helps identify the key gaps in irradiated materials property data (and emphasise the severe need for a fully populating irradiated materials database).

中文翻译：

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面向偏滤器等离子体的组件实现可靠的分析设计——非弹性评估指南（第二部分：辐照）

本文提供了评估面向等离子体组件 (PFC) 的结构完整性的指南，这些组件在经过两个全功率年照射到 DEMO 中预期的水平时。该论文是由 3 部分组成的论文的第二部分，该论文描述了 EuroFusion DEMO 偏滤器组 (WPDIV) 非弹性分析程序 (IAP)，该程序旨在改进对 PFC 的评估，特别是那些由 CuCrZr 散热器冷却的钨铠装构造的材料（带有铜）夹层）。本文首先回顾了第 1 部分论文中详细介绍的 IAP 方法，然后详细回顾了有关材料特性（热导率、膨胀和应力应变曲线）和材料极限数据（断裂-应变）的有限相关辐照材料数据。应变、断裂韧性和疲劳强度）。该数据用于对类 ITER 偏滤器“整体”PFC（带有贯穿 CuCrZr 管的钨块）进行 14dpa（CuCrZr）和 4dp（钨）辐射时的结构完整性评估示例。该评估使用 IAP 方法来确定设计对 CuCrZr 管中延展性耗尽、快速断裂、疲劳和棘轮、铜夹层延展性耗尽以及钨铠装脆性断裂等失效的敏感性。这些方法确保包括材料极限水平和材料特性变化的贡献。该论文记录了将现有辐照材料数据扩展到预期的 dpa 和温度范围所需的外推。该评估暴露了整体式设计在应对辐照引起的铜延展性和钨强度急剧下降方面的重大缺陷。这说明，与未辐照条件相比，辐照时保持结构完整性对 PFC 设计构成更严格的约束，因此应在未来的设计研究中优先考虑。尽管本文的主要目的是提出评估方法，但它也有助于确定辐照材料特性数据中的关键差距（并强调迫切需要一个完整的辐照材料数据库）。