DAMAGE OF FUSION MATERIALS UNDER VARIABLE IRRADIATION CONDITIONS

因此，它是预期的，因为辐射条件的这种情况与温度和中子通量在聚变反应器的操作下发生了很大的变化，大多数辐射实验是在聚变材料的开发中被运送出来的。因此，在这一项目中，辐射实验是根据各种温度条件进行的，以确定各种条件下的基本损伤机制。在纯金属和合金的情况下，在预期的情况下，辐射实验是根据各种温度条件进行的。这一点被揭示为，在温度变化期间，国际原子和真空的暂时不平衡导致了极大影响的累积损伤，并通过比较实验结果和数值计算来衡量。基于速率理论的缺陷累积。在另一方的情况下，在P-修改的奥斯汀不锈钢的情况下，已知为高swelling抗性材料对Fe-D22-D2 P属性的下沉效应，噪声很容易形成在低温度下短的前irradiation，因为不稳定的Fe-D22-D2 P precipitates During the Pre-irradiation。它还找到了具有P增强稳定性的Fe-D22-D2 P precipitates even in the pre-irradiation at low temperature.它已清除了温度变异对Ti-oxide的影响在V-4 Cr-4 Ti合金中的重要作用。在低温度下的预辐射增强了高密度钛氧化物的形成，这一结果对材料的结构和硬件的大影响。这也被揭示了，即通过特殊表面表面对氧化物渗透的抑制作用是可以独立考虑的，因为辐射损伤的进一步研究。因此，我们将建立一种方法来预防氧气渗透在V-4Cr-4 T合金中的温度变异效应，并继续研究。

Though it is expected that the irradiation conditions such as the temperature and the neutron flux are change widely under operation of fusion reactors, most of the irradiation experiments for fusion material development have been carried out at constant conditions. In this projects, therefore, irradiation experiments were performed at various temperature conditions to understand the fundamental damage mechanism under various conditions.In the case of pure metals and alloys, where no segregation are expected, it was revealed that the temporal unbalance of interstitial atoms and vacancies during the change of the temperature greatly affected the accumulation of damage by comparing the experimental results and numerical calculation of defect accumulation based on the rate theory.On the other hand, in the case of P-modified austenitic stainless steel, which is known as high swelling resistance material due to the sink effects of FeィイD22ィエD2P properties, voids are formed easily by short pre-irradiation at low temperature, because of the formation of unstable FeィイD22ィエD2P precipitates during the pre-irradiation. It was also found that co-addition of Ti with P enhanced the stability of FeィイD22ィエD2P precipitates even in the pre-irradiation at low temperature.It was cleared that the effects of temperature variation on the formation of Ti-oxide is important in the V-4Cr-4Ti alloy. Pre-irradiation at low temperature enhances the formation of high density Ti-oxides, and this results in the large influence on the structure and hardiness of the material. It was also revealed that the suppression of penetration of oxygen through the specimen surfaces is indispensable for the further studies of radiation damage. We will therefore establish the method for the prevention of oxygen penetration at first and continue the studies on the temperature variation effects in the V-4Cr-4T alloy.