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Post-Irradiation Examination of ~(237)Np Targets for ~(238)Pu Production

机译:〜(238)Nu生产的〜(237)Np靶的辐照后检查

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Oak Ridge National Laboratory is recovering the US ~(238)Pu production capability and the first step in the process has been to evaluate the performance of a ~(237)Np target cermet pellet encased in an aluminum clad. The process proceeded in 3 steps; the first step was to irradiate capsules of single pellets composed of NpO_2 and aluminum power to examine their shrinkage and gas release. These pellets were formed by compressing sintered NpO_2 and aluminum powder in a die at high pressure followed by sintering in a vacuum furnace. Three temperatures were chosen for sintering the solution precipitated NpO_2 power used for pellet fabrication. The second step was to irradiate partial targets composed of 8 pellets in a semi-prototypical arrangement at the two best performing sintering temperatures to determine which temperature gave a pellet that performed the best under the actual planned irradiation conditions. The third step was to irradiate ~50 pellets in an actual target configuration at design irradiation conditions to assess pellet shrinkage and gas release, target heat transfer, and dimensional stability. The higher sintering temperature appeared to offer the best performance after one cycle of irradiation by having the least shrinkage, thus keeping the heat transfer gap between the pellets and clad small minimizing the pellet operating temperature. The final result of the testing was a target that can meet the initial production goals, satisfy the reactor safety requirements, and can be fabricated in production quantities. The current focus of the program is to verify that the target can be remotely dissembled, the pellets dissolved, and the ~(238)Pu recovered. Tests are being conducted to examine these concerns and to compare results to code predictions. Once the performance of the full length targets has been quantified, the pellet ~(237)Np loading will be revisited to determine if it can be increased to increase ~(238)Pu production.
机译:橡树岭国家实验室正在恢复美国〜(238)Pu的生产能力,该过程的第一步是评估包裹在铝包层中的〜(237)Np目标金属陶瓷粒料的性能。该过程分3个步骤进行:第一步是辐照由NpO_2和铝粉组成的单个药丸的胶囊,以检查其收缩和气体释放。这些粒料是通过在模具中在高压下压缩烧结的NpO_2和铝粉,然后在真空炉中烧结而形成的。选择三个温度以烧结用于颗粒制造的溶液沉淀的NpO_2粉末。第二步是在两个性能最佳的烧结温度下以半原型布置照射由8个小球组成的部分靶材,以确定哪个温度使小球在实际计划的照射条件下表现最佳。第三步是在设计辐照条件下以实际目标配置辐照〜50个颗粒,以评估颗粒收缩和气体释放,目标传热和尺寸稳定性。较高的烧结温度似乎具有最小的收缩率,因此在一个辐射周期后,可以提供最佳的性能,从而使粒料之间的传热间隙保持较小,并且包覆层很小,从而将粒料的工作温度降至最低。测试的最终结果是可以满足初始生产目标,满足反应堆安全性要求并可以量产的目标。该计划目前的重点是验证可以远程分解目标物,溶解颗粒并回收〜(238)Pu。正在进行测试以检查这些问题并将结果与​​代码预测进行比较。一旦确定了全长靶标的性能,将重新考虑〜(237)Np颗粒的负载量,以确定是否可以增加〜(238)Pu的产量。

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