Department of Nuclear Engineering and Health Physics, Idaho State University, Pocatello, ID 83209-8060, USA.
Health Phys. 2012 Jul;103(1):70-9. doi: 10.1097/HP.0b013e31824ac627.
The U.S. Transuranium and Uranium Registries' tissue donors 0202 and 0407 are the two most highly exposed of the 18 registrants who were involved in the 1965 plutonium fire accident at a defense nuclear facility. Material released during the fire was well characterized as "high fired" refractory plutonium dioxide with 0.32-μm mass median diameter. The extensive bioassay data from long-term follow-up of these two cases were used to evaluate the applicability of the Human Respiratory Tract Model presented by International Commission on Radiological Protection in Publication 66 and its revision proposed by Gregoratto et al. in order to account for the observed long-term retention of insoluble material in the lungs. The maximum likelihood method was used to calculate the point estimates of intake and tissue doses and to examine the effect of different lung clearance, blood absorption, and systemic models on the goodness-of-fit and estimated dose values. With appropriate adjustments, Gregoratto et al. particle transport model coupled with the customized blood absorption parameters yielded a credible fit to the bioassay data for both cases and predicted the Case 0202 liver and skeletal activities measured postmortem. PuO2 particles produced by the plutonium fire are extremely insoluble. About 1% of this material is absorbed from the respiratory tract relatively rapidly, at a rate of about 1 to 2 d (half-time about 8 to 16 h). The remainder (99%) is absorbed extremely slowly, at a rate of about 5 × 10(-6) d (half-time about 400 y). When considering this situation, it appears that doses to other body organs are negligible in comparison to those to tissues of the respiratory tract. About 96% of the total committed weighted dose equivalent is contributed by the lungs. Doses absorbed by these workers' lungs were high: 3.2 Gy to AI and 6.5 Gy to LNTH for Case 0202 (18 y post-intake) and 3.2 Gy to AI and 55.5 Gy to LNTH for Case 0407 (43 y post-intake). This evaluation supports the Gregoratto et al. proposed revision to the ICRP 66 model when considering situations of extremely insoluble particles.
美国超铀元素和铀注册中心的组织捐献者 0202 和 0407 是 18 名参与 1965 年国防核设施钚火灾事故的注册者中受照射最高的两个人。火灾中释放的物质被很好地描述为“高燃”难熔二氧化钚,其质量中值直径为 0.32μm。对这两例长期随访的广泛生物测定数据进行了评估,以检验国际放射防护委员会在出版物 66 中提出的人体呼吸道模型及其 Gregoratto 等人提出的修订版的适用性,以便解释观察到的肺部内不溶性物质的长期滞留。最大似然法用于计算摄入量和组织剂量的点估计值,并研究不同的肺部清除率、血液吸收和全身模型对拟合优度和估计剂量值的影响。通过适当调整,Gregoratto 等人的粒子传输模型与定制的血液吸收参数相结合,对这两个病例的生物测定数据进行了可信拟合,并预测了病例 0202 的肝脏和骨骼活性在死后测量值。钚火产生的 PuO2 颗粒极难溶解。约有 1%的这种物质相对较快地从呼吸道吸收,吸收率约为 1 至 2 天(半衰期约为 8 至 16 小时)。其余(99%)吸收极其缓慢,吸收率约为 5×10(-6)天(半衰期约为 400 年)。考虑到这种情况,与呼吸道组织相比,其他器官的剂量似乎可以忽略不计。总承诺加权剂量当量的约 96%来自肺部。这些工人肺部吸收的剂量很高:病例 0202(摄入后 18 年)的 AI 和 LNTH 分别为 3.2Gy 和 6.5Gy,病例 0407(摄入后 43 年)的 AI 和 LNTH 分别为 3.2Gy 和 55.5Gy。当考虑到极难溶性颗粒的情况时,这一评估支持 Gregoratto 等人对 ICRP 66 模型的修订。