俄罗斯氧化物乏燃料电沉积流程研究进展

高温熔盐干法后处理以熔盐作为电解质,通过电解精炼和电沉积回收核燃料中的铀和钚。目前,俄罗斯、美国、日本、韩国和欧盟等国均在积极发展乏燃料高温熔盐干法后处理技术的研究,其中俄罗斯的金属氧化物核燃料电沉积流程是经典的流程之一。本文对俄罗斯原子反应堆研究所(Research Institute of Atomic Reactors, RIAR)发展的氧化物乏燃料高温熔盐电沉积干法后处理的发展现状、流程及特点进行了综述。     

俄罗斯氧化物乏燃料电沉积流程研究进展

高温熔盐干法后处理以熔盐作为电解质，通过电解精炼和电沉积回收核燃料中的铀和钚。目前，俄罗斯、美国、日本、韩国和欧盟等国均在积极发展乏燃料高温熔盐干法后处理技术的研究，其中俄罗斯的金属氧化物核燃料电沉积流程是经典的流程之一。本文对俄罗斯原子反应堆研究所（Research Institute of Atomic Reactors,RIAR）发展的氧化物乏燃料高温熔盐电沉积干法后处理的发展现状、流程及特点进行了综述。     

高温熔盐中氧化物乏燃料的电化学还原研究进展

干法后处理流程可应用于快堆乏燃料后处理。由美国开发的熔盐电解精炼流程是目前最具应用前景的干法后处理流程之一。为了将电解精炼流程应用于氧化物乏燃料后处理,需要将氧化物乏燃料转化为金属。目前电化学还原是应用最广的氧化物乏燃料还原方法,但是该过程仍然存在亟待解决的关键科学与技术问题。本文针对氧化物乏燃料电化学还原研究进展进行综合阐述,主要包括过程简介、研究现状及电化学还原机理等几个方面。     

熔盐电解法乏燃料干法后处理技术研究进展

熔盐电解法是目前最有前途的干法后处理技术,适合于处理氧化物和金属等不同类型乏燃料。熔盐电解法主要包括四个核心流程,即首端处理、电解还原、电解精炼和提取以及废物处理。本文以国际上最新的研究进展为蓝本,综述熔盐电解法乏燃料后处理技术的基本流程以及待解决的关键问题。     

干法后处理流程中电解精炼设备研发进展北大核心CSCD

高燃耗快堆乏燃料具有高钚含量、强放射性、高释热率等特点。基于溶剂萃取原理的水法后处理工艺存在溶剂易辐解等问题,宜对高燃耗快堆乏燃料采用干法后处理工艺进行处理。熔盐电解干法工艺采用耐辐照的无机盐为介质,通过电化学方法分离回收锕系元素,是最具应用前景的干法后处理技术。在熔盐电解干法工艺流程中,承担锕系元素分离任务的电解精炼单元是核心环节。本文调研了乏燃料干法后处理过程中电解精炼设备的研发进展,分析了电解精炼设备关键技术和发展趋势,为我国快堆乏燃料电解精炼设备的研发提供了参考。     

LiF对LiCl-KCl熔盐中钆微观结构的影响

正电解精炼已成为干法后处理的首选技术路线,因此研究离子在熔盐中的电化学行为对干法后处理尤为重要。本工作测定了LiF加入LiCl-KCl熔盐前后对钆、铽还原电位的影响,发现加入LiF后钆、铽的还原电位差由原来的6mV变为67mV,增大了11倍多。用电化学和光谱的方法得到了熔盐中离子的配位结构,发现在LiCl-KCl-GdCl_3(5mol%)/TbCl_3(5mol%)熔盐中为[GdCl_6]~(3-)、[TbCl_6]~(3-)的正八面体结构,其拉曼图谱如图1所     

An（Ⅲ）及Ln（Ⅲ）萃取分离工艺研究进展

<正>为实现真实高放废液的非α化,需要分离出高放废液中以Am、Cm为代表的An(Ⅲ)。根据前期研究,已通过串级实验判断了TODGA+TBP流程符合本课题的需求,并进一步优化了工艺参数;第二步要实现An(Ⅲ)与Ln(Ⅲ)的分离,在反萃取剂PTD的稳定性及单级分离性能研究结果的基础上,前期工作确定了台架实验工艺参数。结合An(Ⅲ)与Ln(Ⅲ)共萃取分离流程,并     

影响CaCl2-NaCl熔盐电脱氧法制备金属Zr的工艺条件

将氧化物转化为金属是熔盐电解精炼干法后处理氧化物乏燃料流程的关键步骤之一。在等摩尔CaCl₂-NaCl混合熔盐体系中,以石墨棒为阳极,采用高温烧结后的ZrO₂模拟UO₂开展了电脱氧制备金属Zr的FFC剑桥工艺条件优化。研究了工艺条件（槽电压、电解时间、烧结温度和电解温度等）对电脱氧制备Zr的影响。采用场发射扫描电子显微镜(SEM)和X射线衍射(XRD)分别分析了电解前后ZrO₂阴极的微观结构和物相组成。优化后的工艺条件为：电压3.4 V、电解时间12 h、烧结温度900 ℃和电解温度722 ℃。同时,研究结果表明, ZrO₂电脱氧还原为Zr时,存在中间产物CaZrO₃和ZrO。     

氯化锂熔盐中八氧化三铀电解还原基础研究

将氧化物乏燃料直接电解还原为粗金属的过程是目前以电解还原-电解精炼为特征的主流干法后处理流程的重要步骤。二氧化铀（UO₂）是乏燃料的最主要成分,将致密的UO₂芯块转化为八氧化三铀（U₃O₈）粉末后,再进行电化学还原能有效提高还原速率。因此,以U₃O₈为研究对象,开展其在氯化锂（LiCl）熔盐中的电解还原机理研究,对后处理干法流程的开发具有重要的现实意义。本文在650 ℃的LiCl熔盐中,采用循环伏安法和恒电位电解法,研究U₃O₈的电解还原行为;对电解后的样品,运用XRD、SEM等手段分析其组成和形貌,并推测相应的还原机理。     

LiF对LiCl-KCl熔盐中钆电解精炼的影响

正熔盐电解精炼干法后处理技术受到越来越多核能国家的关注,以较高的去污系数从乏燃料中回收铀钚已成为研究热点。根据之前的研究发现,LiF加入LiCl-KCl熔盐前后对钆、铽的还原电位有影响,以此为理论基础,进行了LiF加入LiCl-KCl熔盐前后对钆、铽电解精炼的影响。图1为LiF加入前后的电解曲线,加入LiF后进行钆、铽电解精炼时两种熔盐体系所得到的阴极产物示于图2。表1列出不同金属样品中的元素含     

A novel chromatographic separation technique using tertiary pyridine resin for the partitioning of trivalent actinides and lanthanides

A novel chromatographic separation technique using a tertiary pyridine type resin has been applied to the partitioning of the trivalent actinides (An) and lanthanides (Ln) and several successful results have been shown. In an alcoholic hydrochloric acid system, the trivalent An were clearly separated from the Ln, while no such group separation was achieved in an alcoholic nitric acid system. On the other hand, the nitric acid system was more effective for the intragroup (i.e. individual) separation of the trivalent An and the Ln than the hydrochloric acid system. On the basis of these results, a novel concept for the partitioning of the trivalent An and Ln using the present separation technique and its flowchart have been proposed with its advantages and disadvantages.     

Modeled salt density for nuclear material estimation in the treatment of spent nuclear fuel

Spent metallic nuclear fuel is being treated in a pyrometallurgical process that includes electrorefining the uranium metal in molten eutectic LiCl-KCl as the supporting electrolyte. We report a model for determining the density of the molten salt. Material balances account for the net mass of salt and for the mass of actinides present. It was necessary to know the molten salt density, but difficult to measure. It was also decided to model the salt density for the initial treatment operations. The model assumes that volumes are additive for the ideal molten salt solution as a starting point; subsequently, a correction factor for the lanthanides and actinides was developed. After applying the correction factor, the percent difference between the net salt mass in the electrorefiner and the resulting modeled salt mass decreased from more than 4.0% to approximately 0.1%. As a result, there is no need to measure the salt density at 500 °C for inventory operations; the model for the salt density is found to be accurate.     

光谱学方法在锕系/镧系元素配位化学研究中的应用

锕系/镧系金属离子的配位化学对于控制其在后处理流程中的走向、开发新型萃取剂及反萃剂、预测长寿命锕系金属离子在环境中的迁移行为、降低其在生物体中的毒性均有重要意义。光谱学方法是配位化学研究的重要手段,不仅可用来测定配位反应热力学数据,还能提供配位模式、配合物键长、键角等信息。本文在概述光谱学方法用于锕系/镧系元素配位化学研究最新进展的基础上,重点介绍荧光光谱和拉曼光谱在配合物热力学数据测定及结构分析方面的应用,并展望多光谱联合研究方法在锕系/镧系元素配位化学研究中的应用前景。     

Electrodeposition of Uranium and Transuranic Elements onto Solid Cathode in LiCl-KCl/Cd System for Pyrometallurgical Partitioning

A pyrometallurgical partitioning process is being developed for recovering transuranic elements (TRUs) from high-level liquid waste. In the process, actinides are separated from fission product, especially rare earth elements (REs), by means of an electrorefining technique or a reductive-extraction technique. In this study, electrorefining experiments were carried out in LiClKCl/Cd system to recover actinides from salt bath containing actinides and REs. Uranium and neptunium could be depleted from the salt bath and recovered onto a solid cathode with high collection efficiency and high selectivity. Plutonium and americium, however, were difficult to be recovered at high current efficiency because reduction of Nd³⁺ to Nd²⁺ at about—1.7V consumed cathodic current prior to the deposition of Pu or Am. The rotation of the cathode had rather negative effect against deposition of Am and Pu in case of coexistence of much amount of Nd because Nd²⁺ was removed from the cathode surface quickly and the reaction of Nd³⁺ to Nd²⁺ was promoted. At higher current density, Pu and Am could be recovered onto solid cathode but current efficiency became too low. The result indicated that electrorefining technique in the pyro-partitioning was effective for U and Np but not for Pu and Am.     

Selective adsorption of trivalent actinides from lanthanides onto activated carbons in acidic aqueous solution

Adsorption of trivalent actinides (An(III)) and lanthanides (Ln(III)) in acidic aqueous solution using activated carbons was investigated. Activated carbons exhibited significantly selective adsorption to An(III) over Ln(III) in acidic aqueous solution from about pH 1-4, independently of the starting materials, activation methods and specific surface areas.     

Actinide recycling by pyro-process with metal fuel FBR for future nuclear fuel cycle system

Pyro-metallurgical technology is one of potential devices for future nuclear fuel cycle. Not only economic advantage but also environmental safety and strong resistance for proliferation are required for the fuel cycle. In order to satisfy the requirement, actinides recycling applicable to LWR and FBR cycles by pyro-process has been developed since more than ten years in CRIEPI. The main technology is electrorefining for U and Pu separation and reductive-extraction for TRU separation, which can be applied on oxide fuels through reduction process as well as metal fuels. The application of this technology on separation of TRU in HLLW through chlorination could contribute to the improvement of public acceptance on the geologic disposal.

The main achievements are summarized as follows:

• -|The elemental technologies, such as electrorefining, reductive extraction, injection casting and salt waste treatment and solidification, have been developed successfully with lots of experiments

• -|The fuel dissolution into molten salt and uranium recovery on solid cathode for electrorefining have been demonstrated by engineering scale facility in Argonne National Laboratory by using spent fuels and in CRIEPI by uranium tests.

• -|Single element tests, using actinides, showed the Li reduction to be technically feasible, remaining the subjects of technical feasibility on multi-elements system and on effective recycle of Li by electrolysis of Li₂O.

• -|Concerning on the treatment of HLLW for actinide separation, the conversion to chlorides through oxides has been also established through uranium tests.

• -|It is confirmed that more than 99% of TRU nuclides can be recovered from the high level liquid waste by TRU tests

• -|Through these studies, the process flow sheets for reprocessing of metal and oxide fuels and for partitioning of TRU separation have been established.

The subjects to be emphasized for further development are classified into three categories, that is, process development (demonstration), technology for engineering development, and supplemental technology.

The metal fuel FBR has a high potential for recycling actinides by integration with pyro-reprocessing. Alloys of U-Pu-Zr with minor actinides are investigated from points of fuel properties. The miscibility and other characteristics suggest that the maximum content up to ca. 5 wt% of minor actinides is allowable in the matrix. Nine pins of metal fuel including minor actinides are ready for irradiation at Phenix fast reactor.     

基于分子力场的镧系和锕系元素 分子动力学研究进展

简要概述了镧系和锕系元素关键种态的力场发展及其应用。早期主要采用非极化力场研究镧系和锕系离子的溶剂化结构,取得了与实验吻合较好的结果。近年来发展起来的极化力场因考虑了对极化效应的处理而可获得更精确的结果,并在镧系和锕系溶液动力学研究中得到了初步的应用。本文从水溶液动力学、f区元素萃取相关的配位动力学、环境与健康相关的动力学等三个方面简要总结了近年来部分在分子力场水平上研究镧系和锕系溶液动力学和生物无机化学的工作。     

Electrorefining of metallic fuel with burn-up of ~7 at% in a LiCl-KCl melt

Electrorefining of irradiated metallic fuels (burn-up ~ 7 at%) in a LiCl-KCl melt at 773 K was successfully demonstrated: Actinides in the fuels were anodically dissolved in the melt. Both a selective U metal deposition on a solid cathode and a grouped recovery of actinides, U, Pu, Np, Am, and Cm, in a liquid Cd cathode were confirmed. The behavior of fission products, such as lanthanides, alkali metals, alkaline earth metals, and noble metals, were also investigated. It was found that the behaviors of actinides and fission products in the electrorefining of the fuels with ~ 7 at% burn-up were similar to those in electrorefining of fuels with ~ 2.5 at% burn-up.     

Study of thermodynamic properties of Np-Al alloys in molten LiCl-KCl eutectic

Pyrochemical methods are investigated worldwide within the framework of Partitioning and Transmutation concepts for spent nuclear fuel reprocessing. Electroseparation techniques in a molten LiCl-KCl are being developed in ITU to recover all actinides from a mixture with fission products. During the process, actinides are selectively electrochemically reduced on a solid aluminium cathode, forming solid actinide-aluminium alloys. This work is focused on the thermodynamic properties of Np-Al alloys in a temperature range of 400-550 °C and on the characterisation of the structure and chemical composition of deposits obtained by electrodeposition of Np on solid Al electrodes in a LiCl-KCl-NpCl₃ melt. Cyclic voltammetry and open circuit chronopotentiometry have been used to examine the electrochemical behaviour of Np on inert W and reactive Al electrodes. Gibbs energies, enthalpy and entropy of formation and standard electrode potentials of Np-Al alloys were evaluated and compared with ab initio calculations. Galvanostatic electrolyses at 450 °C were carried out to recover Np onto Al plates and the solid surface deposits were characterised by XRD and SEM-EDX analyses. Stable and dense deposits consisting of NpAl₃ and NpAl₄ alloys were identified. In addition, the conversion of NpO₂ to NpCl₃ is described, using chlorination of the oxide in a molten salt media by pure chlorine gas.