Plasma facing components inside future nuclear fusion reactors are subjected to a high heat load and intense irradiation conditions. Using advanced computational material models, several problems can be solved that reflect tungsten monoblocks under fusion relevant loading scenarios. This allows for the identification of the conditions under which material failure is probable. The material model and parameters are identified such that the mechanical behaviour is in accordance with the homogenized behaviour of a previously developed crystal plasticity model on the microscopic scale. The heterogeneous stress field that follows is analysed in order to assess the probability of material failure, which is typically reflected by unstable crack propagation. Since fracture is an inherently multi-scale problem, critical regions are analysed in detail by means of a representative volume element. The resulting analysis reveals that in case the stress relaxation in the monoblock under the applied static heat load is complete, the probability of unstable crack propagation can reach values close to 35%. Finally, the impact of prolonged neutron irradiation is simulated by means of a cluster dynamics model. Although irradiation drastically increases the brittleness of tungsten, its impact on the overall monoblock performance remains limited.

未来核聚变反应堆内面向等离子体的组件会受到高热负荷和强烈辐照条件的影响。使用先进的计算材料模型，可以解决几个问题，这些问题反映了融合相关加载场景下的钨单体。这允许识别可能发生材料故障的条件。确定材料模型和参数，使得机械行为与先前开发的晶体塑性模型在微观尺度上的均质行为一致。分析随后的异质应力场以评估材料失效的概率，这通常由不稳定的裂纹扩展反映出来。由于断裂本质上是一个多尺度问题，通过具有代表性的体积元素对关键区域进行详细分析。结果分析表明，如果在施加的静态热载荷下单体中的应力松弛完成，则不稳定裂纹扩展的概率可达到接近 35% 的值。最后，通过簇动力学模型模拟了长时间中子辐照的影响。尽管辐照大大增加了钨的脆性，但它对整体整体性能的影响仍然有限。长时间中子辐照的影响是通过集群动力学模型模拟的。尽管辐照大大增加了钨的脆性，但它对整体整体性能的影响仍然有限。长时间中子辐照的影响是通过集群动力学模型模拟的。尽管辐照大大增加了钨的脆性，但它对整体整体性能的影响仍然有限。