ORANO Mining, R&D Dpt, 125 Avenue de Paris, F-92330, Châtillon, France.
DEN, Service d'Etude du Comportement des Radionucléides (SECR), CEA, Université Paris-Saclay, F-91191, Gif-sur-Yvette, France.
J Environ Radioact. 2020 Jul;218:106223. doi: 10.1016/j.jenvrad.2020.106223. Epub 2020 Mar 13.
The mill tailings from uranium mines constitute very low-level, long-lived, radioactive process waste. Their long-term management therefore requires a good understanding of the geochemical mechanisms regulating the mobility of residual uranium and radium-226. This article presents the results of the detailed characterization of the tailings resulting from the dynamic leaching processes used on the ore of the La Crouzille mining division and stored at the Bellezane site (Haute-Vienne, France) for over 25 years. A multi-scalar and multidisciplinary approach was developed based on a study of the site's history, on the chemical, radiological and mineralogical characterizations of the solid fraction of the tailings, and on porewater analyses. These were complemented by thermodynamic equilibrium models to predict the long-term mobility of U and Ra. Weakly acidic (pH = 6.35) and oxidizing (Eh = 138 mV/SHE) porewaters had a sulfated-magnesian facies ([SO] = 43 mmol/L; [Mg] = 33 mmol/L) with an accessory calcium bicarbonate component (TIC = 25 mmol/L; [Ca] = 13 mmol/L) and dissolved concentrations of uranium and Ra of 12 × 10 mol/L and 0.58 Bq/L respectively. Ultra-filtration at 10 kDa indicated the absence of colloidal phases. The characterization of the tailings confirmed their homogeneity from a radiological, chemical and mineralogical point of view. The residual U and Ra concentrations measured in the solid were 160 ppm and 25 Bq/g respectively, in accordance with the initial ore grades and mill yields, or more than 99% of the total stock. In terms of chemical and mineralogical composition, the tailings were mainly composed of minerals from the granitic ore (quartz, potassium feldspar, plagioclases and micas) in association with their weathering products (smectite and ferric oxyhydroxides) and with neo-formed minerals following rapid diagenesis after neutralization of the tailings before their emplacement (gypsum and barite). All these minerals are effective traps for the retention of U and Ra. The uranium is distributed partly in micrometer scale uraninite and coffinite refractory phases embedded in grains of quartz, and partly sorbed to smectite and ferric oxyhydroxides. The Ra on the other hand is trapped mainly within the barite. The aqueous concentrations of U and Ra could be described using a thermodynamic approach so that their long-term mobility can subsequently be assessed by modeling. The paragenesis of the tailings could be seen to be stable over time with the exception of neo-formed gypsum and calcite, which will gradually dissolve. The presence of retention traps offering surplus capacity, i.e. smectite, ferric oxyhydroxides and barite, will maintain the U and the Ra at very low aqueous concentrations, even under oxidizing conditions. Moreover, the low permeability of the mill tailings leads, in the case of Ra, to behavior dictated only by the radioactive decay.
铀矿尾矿属于低水平、长寿命的放射性工艺废物。因此,需要很好地理解控制残余铀和镭-226 迁移性的地球化学机制,以对其进行长期管理。本文介绍了对来自铀矿动态浸出过程的尾矿进行详细特征描述的结果,这些尾矿在法国 Haute-Vienne 的 Bellezane 地点储存了 25 年以上。基于对场地历史的研究、尾矿固体部分的化学、放射性和矿物学特征以及孔隙水分析,开发了一种多尺度和多学科的方法。这些方法还辅以热力学平衡模型,以预测 U 和 Ra 的长期迁移性。弱酸性(pH = 6.35)和氧化(Eh = 138 mV/SHE)孔隙水具有硫酸盐-镁质相([SO] = 43 mmol/L;[Mg] = 33 mmol/L),并具有辅助的碳酸钙碳酸氢盐成分(TIC = 25 mmol/L;[Ca] = 13 mmol/L),铀和镭的溶解浓度分别为 12 × 10 mol/L 和 0.58 Bq/L。在 10 kDa 时进行的超滤表明不存在胶体相。尾矿的放射性、化学和矿物学特征表明其具有均一性。固体中测量的残余 U 和 Ra 浓度分别为 160 ppm 和 25 Bq/g,这与初始矿石品位和磨矿收率一致,或者说超过了总库存的 99%。从化学和矿物学组成来看,尾矿主要由花岗岩矿石中的矿物(石英、钾长石、斜长石和云母)以及它们的风化产物(蒙脱石和铁氢氧化物)组成,还包含在尾矿中和置后迅速成岩作用中形成的新矿物(石膏和重晶石)。所有这些矿物都是有效捕获 U 和 Ra 的陷阱。铀部分分布在微米级的晶质铀矿和包裹体难溶物相中,嵌入在石英颗粒中,部分则被吸附在蒙脱石和铁氢氧化物上。另一方面,镭主要被捕获在重晶石中。可以使用热力学方法来描述 U 和 Ra 的水溶液浓度,从而可以通过建模来评估它们的长期迁移性。除了逐渐溶解的新形成的石膏和方解石之外,尾矿的共生组合随时间保持稳定。具有过剩容量的保留陷阱,即蒙脱石、铁氢氧化物和重晶石,将使 U 和 Ra 保持在非常低的水溶液浓度,即使在氧化条件下也是如此。此外,由于镭的低渗透率,仅受放射性衰变控制。