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Evaluation of precipitation behavior of zirconium molybdate hydrate

Liang ZHANG, Masayuki TAKEUCHI, Tsutomu KOIZUMI, Izumi HIRASAWA

《化学科学与工程前沿（英文）》 2013年第7卷第1期页码 65-71 doi: 10.1007/s11705-013-1314-9

摘要： In the dissolution step of spent nuclear fuel, there is a world-concern problem that zirconium molybdate hydrate precipitates as a byproduct, and accumulates in some reprocessing equipments. In order to prevent this accumulation, we have developed a new method based on the controlled reaction crystallization of zirconium molybdate hydrate (ZMH) in the reprocessing solution, followed by solid liquid separation. In order to measure the particle size of ZMH, batch crystallization experiments were conducted by varying nitric acid concentration and operating temperature. In result, almost all particle sizes scatter around 1 μm on average, despite the higher concentration of nitric aid and operating temperature, and then small particles grow up as an aggregate sticking to the crystallizer. Moreover, polymorph and color changing were observed by varying the concentration of nitric acid and reaction time. These results suggest that crystal color and adhesiveness are closely related to the particle size of ZMH. And the control of nitric acid concentration and small particle growth would be the useful technique to prevent the ZMH sticking.

关键词： spent nuclear fuel zirconium molybdate hydrate cleaning method accumulation

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中国新一代核能核燃料总体发展战略研究

李冠兴,周邦新,肖岷,焦拥军,任忠鸣

《中国工程科学》 2019年第21卷第1期页码 6-11 doi: 10.15302/J-SSCAE-2019.01.002

摘要：

本文深入分析和研究了国内外压水堆燃料和材料技术，快堆及其他先进堆燃料技术以及核燃料循环相关材料技术发展的现状和趋势，提出了我国压水堆、快堆及其他先进堆核燃料与材料，以及核燃料循环材料发展的目标、发展路线图和重点任务。压水堆是我国21世纪相当长时间内核能发电及能源结构转型的主力堆型。作为压水堆发展重要支撑的核燃料及材料基本实现了国产化，但还没有实现品牌自主化。我国的快堆及快堆核燃料发展面临机遇和挑战，核燃料循环产业面临重大历史性发展机遇和巨大挑战。最后对我国的压水堆、快堆、其他先进堆型核燃料及材料，以及我国核燃料循环材料的发展提出了建议。

关键词：核燃料核材料轻水堆压水堆快堆燃料循环

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PWR-FBR with closed fuel cycle for a sustainable nuclear energy supply in China

XU Mi

《能源前沿（英文）》 2007年第1卷第2期页码 129-134 doi: 10.1007/s11708-007-0016-8

摘要： From the thermal reactor to the fast reactor and then to the fusion reactor; this is the three-step strategy that has been decided for a sustainable nuclear energy supply in China. As the main thermal reactor type, the commercialized development phase of the pressurized water reactor (PWR) has been stepped up. The development of the fast reactor (FBR) is still in the early stage, marked by China experimental fast reactor (CEFR), which is currently under construction. According to the strategy study on the fast reactor development in China, its engineering development will be divided into three steps: the CEFR with a power of 65 MWt/20 MWe; the China prototype fast reactor (CPFR) with a power of 1 500 MWt/600 MWe; and the China demonstration fast reactor (CDFR) with a power of 2 500 3 750 MWt/1 000 1 500 MWe. With regards to the fuel cycle, a 100 t/a PWR spent fuel reprocessing pilot plant and a 500 kg/ a MOX fabrication plant are under construction. A project involving the construction of an industrial reprocessing plant and an MOX fabrication plant are also under application phase.

关键词： reactor development reprocessing MWt/600 demonstration three-step strategy

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先进核燃料技术助推核能复兴

Mitch Leslie

《工程（英文）》 2021年第7卷第11期页码 1508-1510 doi: 10.1016/j.eng.2021.09.002

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Investigation of phosphate adsorption from an aqueous solution using spent fluid catalytic cracking catalyst

Zhen Li, Zhaofu Qiu, Ji Yang, Benteng Ma, Shuguang Lu, Chuanhui Qin

《环境科学与工程前沿（英文）》 2018年第12卷第6期 doi: 10.1007/s11783-018-1082-3

摘要：

Spent FCC catalyst with lanthanum is proposed as a novel P-removal adsorbent.

The spent FCC catalyst exhibits 99% adsorption efficiency for low P-concentration wastewater (C₀<5.0 mg/L).

High affinity, endothermic reaction and fast sorption kinetics are achieved.

The phosphate is adsorbed in the form of LaPO₄ and KH₂PO₄.

关键词： Spent FCC catalyst Phosphate removal Adsorption Lanthanum

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Selective capture and separation of xenon and krypton using metal organic frameworks: a review

《化学科学与工程前沿（英文）》 2023年第17卷第12期页码 1895-1912 doi: 10.1007/s11705-023-2355-3

摘要： Xenon and krypton are widespread useful noble gases in commercial lighting, lasers, electronics, and medical industry. At the same time, radioactive noble gases may proliferate from used nuclear fuel and diffuse in open atmospheres. Metal organic frameworks as hotspot porous materials for gases uptake and separation are considered to be potential solutions. In this review, we comprehensively summarized recent researches on metal organic frameworks for selective capture and separation of xenon and krypton. Particularly, we followed the aspects of different optimal design strategies, including optimal pore/cage size and geometry, open metal sites, ions (anions and cations), and polar functional groups for enhancing the xenon adsorption and separation performances. Meanwhile, a comparison of each strategy and the mechanisms of xenon/krypton separation were pointed out. The separation of krypton from gases mixtures by dual-bed systems was further discussed. Finally, some existing challenges and opportunities for possible real applications were proclaimed.

关键词： metal organic frameworks xenon krypton selective separation used nuclear fuel

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Optimization of methyl orange removal from aqueous solution by response surface methodology using spent

Liangzhi LI,Xiaolin LI,Ci YAN,Weiqiang GUO,Tianyi YANG,Jiaolong FU,Jiaoyan TANG,Cuiying HU

《环境科学与工程前沿（英文）》 2014年第8卷第4期页码 496-502 doi: 10.1007/s11783-013-0578-0

摘要： The effective disposal of redundant tea waste is crucial to environmental protection and comprehensive utilization of trash resources. In this work, the removal of methyl orange (MO) from aqueous solution using spent tea leaves as the sorbent was investigated in a batch experiment. First, the effects of various parameters such as temperature, adsorption time, dose of spent tea leaves, and initial concentration of MO were investigated. Then, the response surface methodology (RSM), based on Box–Behnken design, was employed to obtain the optimum adsorption conditions. The optimal conditions could be obtained at an initial concentration of MO of 9.75 mg·L , temperature of 35.3°C, contact time of 63.8 min, and an adsorbent dosage 3.90 g·L . Under the optimized conditions, the maximal removal of MO was 58.2%. The results indicate that spent tea leaves could be used as an effective and economical adsorbent in the removal of MO from aqueous solution.

关键词： spent tea leaves adsorption response surface methodology methyl orange (MO)

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Preparing graphene from anode graphite of spent lithium-ion batteries

Wenxuan Zhang, Zhanpeng Liu, Jing Xia, Feng Li, Wenzhi He, Guangming Li, Juwen Huang

《环境科学与工程前沿（英文）》 2017年第11卷第5期 doi: 10.1007/s11783-017-0993-8

摘要： With extensive use of lithium ion batteries (LIBs), amounts of LIBs were discarded, giving rise to growth of resources demand and environmental risk. In view of wide usage of natural graphite and the high content (12%–21%) of anode graphite in spent LIBs, recycling anode graphite from spent LIBs cannot only alleviate the shortage of natural graphite, but also promote the sustainable development of related industries. After calcined at 600°Cfor 1 h to remove organic substances, anode graphite was used to prepare graphene by oxidation-reduction method. Effect of pH and N2H4·H2O amount on reduction of graphite oxide were probed. Structure of graphite, graphite oxide and graphene were characterized by XRD, Raman and FTIR. Graphite oxide could be completely reduced to graphene at pH 11 and 0.25 mL N2H4·H2O. Due to the presence of some oxygen-containing groups and structure defects in anode graphite, concentrated H2SO4 and KMnO4 consumptions were 40% and around 28.6% less than graphene preparation from natural graphite, respectively.

关键词： Spent LIBs Graphite Graphite oxide Grapheme

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核爆聚变电站──人类未来能源的希望

彭先觉,刘成安,陈银亮,郭勤,尹文华,白云,陈小伟,屈明

《中国工程科学》 2008年第10卷第1期页码 39-46

摘要：

详细介绍了核爆聚变电站的基本概念、组成、发展简史；提出了解决核爆炸实施安全、烧氘型核装置设计、核燃料生产回收等一系列问题的技术途径；对电站的技术可行性进行了分析论证，并比较了各种作为人类未来能源核能方案的前景。

关键词：核爆聚变电站爆洞喷钠烧氘型核装置核燃料循环

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我国核燃料循环标准化发展战略研究

潘建均,王毅韧,李筱珍,康椰熙,张宏伟,郭建新,郑刚阳,王妍妍

《中国工程科学》 2021年第23卷第3期页码 53-59 doi: 10.15302/J-SSCAE-2021.03.016

摘要：

核燃料循环标准化是核燃料循环产业安全发展、创新发展的重要支撑，特别是在我国进入高质量发展阶段期间，标准化作用显得尤为重要，开展核燃料循环标准化发展战略研究对支撑我国核工业强国建设具有重要战略意义。本文系统分析了国内外核燃料循环标准化的发展现状，从工作机制、发展平衡性、引领作用、保障能力等方面剖析了我国核燃料循环标准化亟待解决的关键问题，并据此提出了今后的主要任务和相关对策建议。研究指出，我国核燃料循环标准化工作今后的七项重点任务为：补齐核燃料循环后段标准短板、加大关键核心技术标准研制、加强先进标准研制、强化前沿基础标准建设、加强安全环保标准建设、深度参与国际标准化工作、强化标准化基础能力建设。最后，本文从将核燃料循环标准化纳入核工业“十四五”规划、健全标准化工作机制、加大经费投入、加强标准化人才队伍建设等方面提出了对策建议。

关键词：核燃料循环高质量发展技术标准基础能力标准国际化

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Highly selective metal recovery from spent lithium-ion batteries through stoichiometric hydrogen ion

Weiguang Lv, Xiaohong Zheng, Li Li, Hongbin Cao, Yi Zhang, Renjie Chen, Hancheng Ou, Fei Kang, Zhi Sun

《化学科学与工程前沿（英文）》 2021年第15卷第5期页码 1243-1256 doi: 10.1007/s11705-020-2029-3

摘要： Spent lithium-ion battery recycling has attracted significant attention because of its importance in regard to the environment and resource importance. Traditional hydrometallurgical methods usually leach all valuable metals and subsequently extract target meals to prepare corresponding materials. However, Li recovery in these processes requires lengthy operational procedures, and the recovery efficiency is low. In this research, we demonstrate a method to selectively recover lithium before the leaching of other elements by introducing a hydrothermal treatment. Approximately 90% of Li is leached from high-Ni layered oxide cathode powders, while consuming a nearly stoichiometric amount of hydrogen ions. With this selective recovery of Li, the transition metals remain as solid residue hydroxides or oxides. Furthermore, the extraction of Li is found to be highly dependent on the content of transition metals in the cathode materials. A high leaching selectivity of Li (>98%) and nearly 95% leaching efficiency of Li can be reached with LiNi Co Mn O . In this case, both the energy and material consumption during the proposed Li recovery is significantly decreased compared to traditional methods; furthermore, the proposed method makes full use of H to leach Li . This research is expected to provide new understanding for selectively recovering metal from secondary resources.

关键词： recycling spent LIBs selective recovery hydrothermal treatment

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Bioleaching of spent Ni-Cd batteries and phylogenetic analysis of an acidophilic strain in acidified

ZHAO Ling, WANG Liang, YANG Dong, ZHU Nanwen

《环境科学与工程前沿（英文）》 2007年第1卷第4期页码 459-465 doi: 10.1007/s11783-007-0073-6

摘要： Biohydrometallurgy is a novel method to recycle discarded batteries, in which sewage sludge is used as microorganisms and culture due to the presence of indigenous . A two-step continuous flow leaching system co

关键词： Biohydrometallurgy discarded indigenous two-step continuous presence

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我国核电战略性新兴产业“十二五”培育与中长期发展展望

郭晴,苏罡

《中国工程科学》 2016年第18卷第4期页码 55-60 doi: 10.15302/J-SSCAE-2016.04.009

摘要：

核电技术产业是我国战略性新兴产业中新能源产业的重要构成部分，发展核电符合我国绿色低碳能源战略。按照科技突破引领产品升级，带动产能提升和产业发展的思路，本文系统地分析“十二五”期间核电技术产业培育和发展成果，重点介绍福岛事故后我国核电产业发展态势和“华龙一号”等先进核电技术的安全和经济特性，提出“十三五”乃至更长时期的发展趋势和方向，包括发展基于快堆的核燃料闭式循环体系，聚变技术发展实现“三步走”战略。通过小型模块化反应堆技术探索核能多用途利用等，实现核电技术产业的规模化、可持续发展，在推动我国经济平稳、持续增长，能源结构和工业结构优化升级方面发挥更大作用。

关键词：核电技术产业战略性新兴产业华龙一号核燃料闭式循环 “三步走”战略

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Special issue: innovative nuclear energy technology

《能源前沿（英文）》 2021年第15卷第4期页码 791-792 doi: 10.1007/s11708-021-0794-4

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An old issue and a new challenge for nuclear reactor safety

F. D’AURIA

《能源前沿（英文）》 2021年第15卷第4期页码 854-859 doi: 10.1007/s11708-021-0729-0

摘要： Nuclear reactor safety (NRS) and the branch accident analysis (AA) constitute proven technologies: these are based on, among the other things, long lasting research and operational experience in the area of water cooled nuclear reactors (WCNR). Large break loss of coolant accident (LBLOCA) has been, so far, the orienting scenario within AA and a basis for the design of reactors. An incomplete vision for those technologies during the last few years is as follows: Progress in fundamentals was stagnant, namely in those countries where the WCNR were designed. Weaknesses became evident, noticeably in relation to nuclear fuel under high burn-up. Best estimate plus uncertainty (BEPU) techniques were perfected and available for application. Electronic and informatics systems were in extensive use and their impact in case of accident becomes more and more un-checked (however, quite irrelevant in case of LBLOCA). The time delay between technological discoveries and applications was becoming longer. The present paper deals with the LBLOCA that is inserted into the above context. Key conclusion is that regulations need suitable modification, rather than lowering the importance and the role of LBLOCA. Moreover, strengths of emergency core cooling system (ECCS) and containment need a tight link.

关键词： large break loss of coolant accident (LBLOCA) nuclear reactor safety (NRS) licensing perspectives basis for design of water cooled nuclear reactors (WCNR)