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首页> 外文期刊>Health Physics: Official Journal of the Health Physics Society >Uranium Aerosol Activity Size Distributions at a Nuclear Fuel Fabrication Plant
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Uranium Aerosol Activity Size Distributions at a Nuclear Fuel Fabrication Plant

机译:在铀气溶胶活动大小分布核燃料加工厂

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Inhalation of uranium aerosols is a concern in nuclear fuel fabrication. Determination of committed effective doses and lung equivalent doses following inhalation intake requires knowledge about aerosol characteristics; e.g., the activity median aerodynamic diameter (AMAD). Cascade impactor sampling of uranium aerosols in the breathing zone of nuclear operators was carried out at a nuclear fuel fabrication plant producing uranium dioxide via ammonium uranyl carbonate. Complementary static sampling was carried out at key process steps. Uranium on impaction substrates was measured using gross alpha counting and alpha spectrometry. Activity size distributions were evaluated for both unimodal and bimodal distributions. When a unimodal distribution was assumed, the average AMAD in the operator breathing zone at the workshops was 12.9-19.3 mu m, which is larger than found in previous studies. Certain sampling occasions showed variable isotope ratios (U-234/U-238) at different impactor stages, indicating more than one population of particles; i.e., a multimodal activity size distribution. When a bimodal distribution (coarse and fine fraction) was assumed, 75-88% of the activity was associated with an AMAD of 15.2-18.9 mu m (coarse fraction). Quantification of the AMAD of the fine fraction was associated with large uncertainties. Values of 1.7-7.1 mu m were obtained. Static sampling at key process steps in the workshops showed AMADs of 4.9-17.2 mu m, generally lower than obtained by breathing zone sampling, when a unimodal distribution was assumed. When a bimodal distribution was assumed, a smaller fraction of the activity was associated with the coarse fraction compared to breathing zone sampling. This might be due to impactor positioning during sampling and sedimentation of large particles. The average committed effective dose coefficient for breathing zone sampling and a bimodal distribution was 1.6-2.6 mu Sv Bq(-1)for(234)U when Type M/S absorption parameters were assumed (5.0 mu Sv Bq(-1)for an AMAD of 5 mu m). The corresponding lung equivalent dose coefficient was 3.6-10.7 mu Sv Bq(-1)(29.9 mu Sv Bq(-1)for an AMAD of 5 mu m). The predicted urinary excretion level 100 d after inhalation intake was found to be 13-34% of that corresponding to an AMAD of 5 mu m. Uranium aerosols generated at a nuclear fuel fabrication plant using ammonium uranyl carbonate route of conversion were associated with larger AMADs compared to previous work, especially when sampling of aerosols was carried out in the operator breathing zone. A bimodal activity size distribution can be used in calculations of committed effective doses and lung equivalent doses, but parameters associated with the fine fraction must be interpreted with care due to large uncertainties.
机译:铀吸入气溶胶的担忧核燃料制造。提交有效的剂量和肺等价的剂量吸入摄入要求了解气溶胶特征;活动中空气动力学直径(哈桑)。级联撞击器铀气溶胶的采样核电站运营商的呼吸区在核燃料制造工厂进行通过铀酰铵生产二氧化铀碳酸盐岩。在关键的流程步骤。压紧基板用总值测量α计数和α谱分析。尺寸分布进行评估的单峰和双峰分布。单峰分布假定,平均水平哈桑在运营商的呼吸区车间是12.9 - -19.3μm,这是更大的比先前的研究中发现的。场合显示变量同位素比值(u - 234 / u - 238)在不同撞击器阶段,显示多个人口的粒子;例如,多通道活动大小分布。当一个双峰分布(粗和细分数)认为,75 - 88%的活动与15.2 - -18.9μm(粗的哈桑分数)。分数与巨大的不确定性。1.7 - -7.1μm的值。在车间的关键流程步骤抽样显示,哈桑的4.9 - -17.2μm,通常较低呼吸区取样,获得的比当一个单峰分布假设。分布假定,一个更小的部分与粗相关联的活动分数比呼吸区取样。这可能是由于撞击器定位中采样和大粒子的沉降。平均有效剂量系数呼吸区采样和双峰分布在1.6 - -2.6μSv Bq (1) (234)当M / S型吸收参数(5.0亩Sv Bq(1)的哈桑5μm)。相应的肺系数等效剂量是3.6 - -10.7μSv Bq(1)(29.9μSv Bq (1)哈桑的5μm)。预测尿排泄100级d吸入摄入后被发现13 - 34%的相应的哈桑5μm。铀核气溶胶生成使用铀酰铵燃料加工厂碳酸盐岩的转换有关大哈桑和以前的工作相比,特别是当气溶胶进行抽样在运营商的呼吸区。可以使用活动大小分布计算的有效剂量和肺等效剂量,但参数相关与细分数必须解释由于巨大的不确定性。

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