压水堆核电站放射性废液的水泥固化研究

本文讨论了用水泥胶结剂固化压水堆含硼废液和酸碱去污液的适用性。碱性废液的固化不存在特殊困难。加氢氧化钠或偏铝酸钠进行中和及促凝可改善含硼废液和酸性去污液与水泥的化学兼容性,缩短浆体的凝固时间。添加30%斜发沸石可增加水泥固化体的机械强度、降低浸出率和减小固化体体积。     

模拟放射性含氟废液水泥固化配方的研究

本文以沸石、硅灰、石英砂为添加剂,按照质量比m（沸石）∶m(硅灰)∶m（石英砂）∶m（水泥）=1∶1∶3∶10配方对模拟放射性含氟废液进行水泥固化。由配方得到的水泥浆流动度和初、终凝时间满足桶内固化要求。测定了水泥固化体28 d的抗压强度、抗浸泡性和抗冻融性实验后的强度损失,进行了抗冲击性能测试和模拟核素浸出实验。结果表明,该配方可有效地固化模拟放射性含氟废液,固化体28 d抗压强度、各项实验强度损失和模拟核素浸出率均满足GB 14569.1-2011的要求。水泥固化体的F^-浸出率很低,XRD显示F^-以CaF₂形式存在。废液中F^-质量分数控制在1%较为合适,此时水泥固化体终凝时间为14 h,F^-的42 d浸出率为2.54×10^-3 cm/d。     

含硼废液水泥固化技术综述

压水堆核电厂含硼废液的处理主要采用水泥固化方法,这些方法大致可分为五种,即常规水泥固化工艺、改进型水泥固化工艺、高减容水泥固化工艺、制粉造粒灌浆固化工艺和高效率固化工艺。通过对各固化工艺特点的分析,提出我国应在制粉造粒灌浆固化工艺方面加强研究。     

模拟非α中低放废液大体积浇注水泥固化的可行性研究

本文对在我国高放废液分离流程中产生的中低放非α废液的大体积浇注水泥固化,在实验室小试条件下进行了可行性研究。结果表明,经浓缩、脱硝及中和处理后,非低α中放废液可用大体积浇注水泥固化进行处理和处置。推荐的固化配方为：水灰比１．０￣１．１,盐灰比０．１８￣０．２０,及占水泥重量０．５％（ｗｔ）的水泥高效缓凝减水剂。固化体第４２ｄＣｓ的浸出率为１０＾－３￣１０＾－５ｃｍ／ｄ,Ｓｒ的浸出率在３．１×１０＾     

放射性废液综合处理车间正式启动运行

放射性废液综合处理车间建成于2003年，其主要功能是通过蒸发浓缩处理中放废液，并最终将废液转化为水泥固化体进行永久处置。该车间生产能力为每天蒸发处理废液12t，生产水泥固化体15桶。该车间建成后，先后进行了冷试验和整改，使该车间具备了设计的生产运行能力，在2004年底，顺利完成了车间的热试验，热试验完成处理废液约100m^3，产生水泥固化体约40桶。     

模拟放射性含硼废液的水泥固化研究

为了比较硫铝酸盐水泥和普通硅酸盐水泥含硼废液的固化,为配方优化提供依据,研究采用两种配方对模拟放射性含硼废液进行水泥固化。测定了固化体28d抗压强度、抗浸泡性、抗冻融性和耐γ辐照试验后的强度损失,进行了模拟核素浸出试验,并对固化体水化产物进行XRD分析。结果表明,两种配方可有效固化模拟含硼废液,固化体28d抗压强度、各项试验强度损失和模拟核素浸出率均满足GB14569.1—93的要求,试验所用的硫铝酸盐水泥配方对Cs＋的滞留能力优于普通硅酸盐水泥配方,固化体中的硼以B(OH)4－形式固溶在钙矾石中。     

核电厂放射性废液水泥固化体的制备北大核心CSCD

针对某核电厂复杂成分的中、低放射性废液水泥固化体制备过程中出现的流动度损失快、泌水分层、凝结时间难控制等问题,通过实验研究掺合料、保水增稠材料、投料顺序等因素对放射性废液水泥固化体流动度、保水性能、凝结时间、固化体性能的影响规律。研制出既满足国家标准GB 14569.1—2011又适用于现有工程装置的放射性废液水泥固化体专用添加剂及配方,即专用添加剂配方为粉煤灰∶稠化粉∶外加剂A质量比=1∶1∶0.15,水泥固化体配方为水泥∶专用添加剂∶废液质量比=1∶0.272∶0.585。     

泡沫去污废液水泥固化研究

报道了泡沫去污废液的水泥固化基础配方实验及其固化体性能研究的结果。通过水泥固化配方筛选试验 ,推荐固化体水灰比为 0 .3。其固化体物理性能和核素浸出性能分别为 :抗压强度 ,2 4 MPa;1 3 4 Cs、60 Co、2 3 8Pu在第 4 2 d的浸出率分别为 9.98× 1 0 - 4、4 .36× 1 0 - 6、1 .4 1× 1 0 - 7cm/ d。     

中放废液大体积浇注水泥固化配方研究

本文研究了后处理厂中放蒸残液和元件脱壳的偏铝酸钠废液大体积浇注水泥固化的特殊工艺配方。实验用525普通硅酸盐水泥,模拟废液中分别含~(134)Cs 和~(85)Sr,其放射性浓度均为3.7×10(?)Bq/L。实验结果表明,选用加 DH 型水泥添加剂的配方可满足大体积浇注固化池内水泥浆“自流式”流平的技术要求,水泥浆的流动度达0.19m 以上;近似绝热养护后的中放蒸残液和偏铝酸钠废液固化体的抗压强度分别大于7.8和10MPa,固化体性能良好,近似绝热养护28天,两种固化体42天时~(134)Cs 和~(85)Sr 的浸出率均低于1.0×10~(-2)cm/d。     

十年来低,中水平放射性废液处理技术的研究和发展

本文扼要地回顾了近十年来低、中放废液处理技术的研究和发展情况。目前,蒸发、离子交换和过滤等方法已广泛地用于处理废液。研究工作的重点是节能与提高效率。由于水泥和沥青固化方法的不足,废液固化研究是针对那些减容比高和固化物性能好的方法。在地质条件许可的情况下,操作简便和价格低廉的固化处置一体化方案已引起某些国家的关注。     

放射性废物水泥固化研究进展

水泥化学的理论研究进展和新的水泥系列、混合材、外加剂及混凝土用纤维材料的研究成果,均可借鉴到放射性废物水泥固化的配方研究中。本文综述硅酸盐水泥、碱活化矿渣水泥、硫铝酸盐水泥等在放射性废物水泥固化研究中的应用现状,介绍火山灰质混合材、外加剂、纤维材料等在提高废物包容量、固化体强度、耐久性和降低核素浸出等方面的研究进展,以期为水泥固化配方的研究与开发提供新的思路。     

Effect of borate concentration on solidification of radioactive wastes by different cements

To investigate the effect of borate on the cementation of radioactive evaporator concentrates, and to provide more data for solidification formula optimization, the simulated borate evaporator concentrates with different borate concentrations (as B) and Na/B ratio (molar ratio) were solidified by sulfoaluminate cement (SAC) and Portland cement (PC), with addition of Ca(OH)₂, zeolite and accelerator or water reducer. The hydration products of solidified matrices were characterized by X-ray diffraction (XRD). The experimental results showed that borate retarded the cement setting for both SAC and PC formulas, and the final setting time prolonged with decrease of Na/B ratio. Borate could enhance the fluidity of the cement mixture. The 28 d compressive strengths of the solidified matrices for both SAC and PC formulas decreased with increase of borate concentration. The XRD patterns suggested that, in the matrices maintained for 28 d, borate did not interfere with the formation of main hydration products of SAC and PC. Borate, in the form of B(OH)⁴⁻, incorporated in ettringite (3CaO·Al₂O₃·3CaSO₄·32H₂O) as solid solution phase. The formula of SAC and PC developed in this study was effective for cementation of the simulated borate evaporator concentrates. However further optimization was required to reduce retarding effect of higher borate concentrations and to extend the practical feasibility for actual evaporator concentrates.     

添加剂对模拟含氟放射性废液水泥固化性能的影响

采用沸石、蛭石、硅灰、石英砂作为添加剂对模拟含氟放射性废液(主要含有Cs+、Sr2+、F-等)水泥固化性能的影响进行了研究。通过添加不同的添加剂,测定水泥浆的初终凝时间、流动度和温升;测定固化体养护28d后的抗压强度及浸泡、冻融试验后的抗压强度,并进行了抗冲击试验和模拟核素浸出试验。通过对比,得到了满足模拟含氟放射性废液水泥固化的配方,该配方制成的水泥固化试块性能达到了GB 14569.1—2011的要求。     

Reprocessing of Liquid Radioactive Wastes,from Nuclear Power Generation,in Autonomous Mobile Purification Facilities

The necessity for and ways to improve the technology for reprocessing liquid radioactive wastes from nuclear power generation are substantiated taking account of the chemical contaminants (petroleum products and products of corrosion). As a general solution, it is proposed that autonomous modular purification facilities, operating on the principle of combining baromembrane and sorption methods, be developed. The basic scheme of the proposed technology and the construction of the purification facilities are described. The results of industrial tests performed on a tanker for collecting liquid wastes from the Pacific Ocean fleet are presented. It is shown that purification to the level of allowed discharges into the sea is possible and that the radioactive concentrates formed can be solidified by cementation. __________ Translated from Atomnaya Energiya, Vol. 99, No. 4, pp. 283–289, October, 2005.     

秦山核电基地放射性废物最小化技术实践与探讨

介绍了秦山核电基地在放射性废物最小化方面的实践。包括建立了蒸汽发生器排污树脂和通风过滤器金属框架清洁解控工作流程;改进了水泥固化线工艺,水泥固化包装容器采用金属桶代替水泥桶;开发了废过滤器芯子暂存衰变法分类处理及一桶装多芯方案;开发了技术废物“三明治”式废物装桶和超级压实提高外包装容器效率等最小化实践。对废液、废树脂、技术废物、有机废液等处理技术进行了比较分析,建议采用废液蒸干压实技术、废树脂蒸汽重整技术、可燃废物和有机废液焚烧技术,预计秦山核电基地废物产生量可由541 m³/a减至约94 m³/a。     

Cobalt(II) cation extraction from solutions containing ethylenediaminetetraacetate and oxalate ions

A new approach to extracting cobalt(II) from non-borate and borate solutions of liquid radioactive wastes containing ligands of ethylenediaminetetraacetate and oxalic acid is proposed. The approach is based on the difference in the stability of complexes of organic ions with metals. Substituting iron(III) for cobalt results in almost complete liberation of Co²⁺ from the complex. Coprecipitation of Co²⁺ with Fe³⁺ in the form of oxohydroxides results in the liberation of Co²⁺ from solution into the solid phase. An excess of Fe³⁺ cations with respect to Co²⁺ and an increase of acidity, processing temperature, and aging time of the solutions at the preliminary stage results in complete liberation of cobalt from the solution for pH ≥ 12.     

Chapter 3: Type and Quantity of Radioactive Waste Destined for Disposal

Abstract

According to the current planning status, radioactive waste with negligible heat generation is destined for storage in the Konrad waste repository in accordance with the Provisional Waste Acceptance Requirements⁽⁴⁾. Waste of this kind occurs in the nuclear fuel cycle, research, medicine and technology. In its original state, the primary wastes of this type have various forms, such as: liquids, concentrates, sludges; ion exchange resins; compressible and/or combustible solids; incompressible solids, e.g. structural material components; filters, filter candles; other types of waste. The radioactive waste is appropriately conditioned and packaged before transport to the waste disposal site. To meet the basic requirements specified in the Waste Acceptance Requirements, primary waste must be solidified, for which the most common solidifying agents are cement and concrete although bitumen is also used. Waste products in decomposing, fermenting or liquid form or which contain a significant fraction in such states are not accepted for disposal.     

磺胺甲恶唑酶联免疫分析方法的建立

本方法建立了磺胺甲恶唑酶联免疫分析方法用以检测动物源性食品中磺胺甲恶唑的残留。利用辣根过氧化物酶（HRP）标记SMX（Sulfamethoxazole ），兔抗SMX抗体制备固相抗体，通过标本中的SMX和一定酶标SMX竞争结合固相抗SMX多抗，标本中SMX的量和显色后的OD450值呈负相关的原理来检测标本中的SMX含量。经方法学鉴定，本方法的灵敏度为0.067μg/L，批内变异<10%，批间变异<20%。牛奶、肉类、鸡蛋、蜂蜜样品的回收率分别为94.9%~116.0%、 82.0%~107.6%、 81.6%~94.9%、89.0%~93.0%，符合免疫分析方法的要求，     

核电站放射性废物混合固化处理可行性研究

基于放射性废物的减量化处理,开展了重水蒸汽回收系统产生的失效干燥剂与浓缩液混合固化冷试配方研究。研究结果表明,混合固化可以实现放射性废物的减容处理,失效干燥剂和浓缩液混合固化的总废物体积包容量为119.1%。