Reif R H
RUST Federal Services, Albuquerque, NM 87106.
Health Phys. 1994 Nov;67(5):545-7. doi: 10.1097/00004032-199411000-00011.
Dissolution rates of thorium from the uranium mill tailings piles at two Department of Energy Uranium Mill Tailings Remedial Action Project (UMTRAP) sites have been evaluated. The thorium dissolution rates were evaluated in vitro using simulated lung fluid. The former uranium mills at the UMTRAP sites employed different chemical processes (acid leach and alkaline pressure leach) to extract the uranium from the ore, and the thorium dissolution rates at these sites were found to be markedly different. A site specific annual limit on intake (ALI) value for 230Th was calculated for the UMTRAP site that was associated with a multiple component dissolution curve.
已对能源部两个铀矿尾矿补救行动项目(UMTRAP)场地的铀矿尾矿堆中钍的溶解速率进行了评估。钍的溶解速率是在体外使用模拟肺液进行评估的。UMTRAP场地以前的铀矿采用了不同的化学工艺(酸浸和碱压浸)从矿石中提取铀,并且发现这些场地的钍溶解速率明显不同。针对与多组分溶解曲线相关的UMTRAP场地,计算了230Th的特定场地年摄入量限值(ALI)值。