Abstract

The release of long-lived radionuclides ¹⁴C and ³⁶Cl , which are key products for assessment of disposal variants (near-surface, buried, or deep) of irradiated graphite, was analyzed. Test material was irradiated graphite from IUGR and RBMK-1000 reactors. Unlike other types of radioactive waste (RAW), graphite has the developed pore structure and, consequently, its effective surface area in contact with the leaching medium is increased in comparison with non-porous materials. With due to regard for the graphite pore structure, the mechanism describing the leaching process is proposed and experimentally substantiated. The parameters numerically characterizing graphite RAW in terms of leaching resistance, independent of the geometric shape of individual fragments (samples) are also introduced. The proposed parameters and an algorithm for their determination are recommended by the authors for use in predictive calculations of the release of radionuclides from graphite under conditions of long-term storage/disposal.

中文翻译：

---

辐照石墨浸出长寿命放射性核素14С和36Сl的过程研究

摘要

长寿命放射性核素¹⁴ C和³⁶的释放分析了作为评估辐照​​石墨处理方式（近表面，埋入或深处）的关键产品Cl的含量。测试材料是来自IUGR和RBMK-1000反应堆的辐照石墨。与其他类型的放射性废物（RAW）不同，石墨具有发达的孔结构，因此与无孔材料相比，其与浸出介质接触的有效表面积增加了。考虑到石墨的孔结构，提出了描述浸出过程的机理并通过实验证实了这一点。还引入了根据抗溶出性在数值上表征石墨RAW的参数，而与单个碎片（样品）的几何形状无关。