采用“施工水源+OF清水池”提前调试淡水厂创新实践

淡水厂为漳州核电自备水厂,给厂区施工、运行生产生活提供保障性供水,但由于淡水管线供水滞后,导致淡水厂不能按时调试。采用“施工水源+OF清水池”方案提前调试的新模式,同时考虑到淡水厂各子项的施工进度,优先建立主系统小循环系统调试,再完成辅助系统调试,最终实现全系统联调,为淡水厂与淡水管线具备供水条件时的无缝对接和顺利接产创造了前提条件。该方案实现了三套一体化临时海水淡化设备落地,使得施工水源的选择可以互为备用,调试用水得到保障。还可以实现以OF清水池作为蓄水池提前给除盐水厂供水,满足除盐水厂调试用水需要。     

核能海水淡化与低温核供热堆的应用

淡水短缺将逐渐成为世界性问题。海水淡化是解决淡水短缺的重要途径之一。利用核能做为海水淡化能源在技术上和经济上都是可行的,并对保护环境有重要意义。本文提出了200兆瓦核供热堆与多效蒸发淡化工艺组合的核能海水淡化方案。着重论述了其安全性和改善其经济性的措施。这种核能海水淡化系统用于北非地区提供淡水具有较好前景。     

HR-200核能海水淡化系统

提出了利用200MW(t)核供热堆与多效蒸发工艺相组合的一种核能海水淡化系统。该系统可产淡水(12～15)×10~4m~3/d。文章论述了200MW(t)核供热堆的设计特点及安全特性,简要介绍了5MW(t)核供热堆的运行经验。指出核能作为海水淡化的替代能源在技术安全上及经济上是可行的。在国内及世界上一些缺水地区具有良好的应用前景。     

核燃料后处理示范厂工艺流程与热实验研究项目圆满完成

<正>11月30日,承担的核燃料后处理示范厂工艺流程与热实验研究项目总结报告正式提交,实验结果完全满足设计指标要求,成功验证了示范厂后处理工艺流程并提出工业化改进建议,标志着该项目圆满完成,为示范厂的设计建设提供了重要技术支持。2015年承担了示范厂后处理工艺流程与热实验研究项目,2018年初启动热实验工作以来,成功开展了三次全流程热实验,其中2019年连续开展了两     

日本计划提高其离心铀浓缩示范厂的生产量

【日本《东京新闻》1980年5月14日报道】日本动力堆·核燃料开发事业团最近将其建在日本冈山县人形岭的离心铀浓缩示范厂(过去一直在投入运行)的年生产能力提高到现有能力的5.5倍。并从5月14日起,打算用两个半月的时间,对该示范厂进行扩建。该离心铀浓缩示范厂是日本动力堆·核燃料开发事业团于去年9月建     

基于逆向质量守恒模拟识别地浸淡化过程中的水岩反应机制

为探讨新疆十红滩砂岩铀矿原位地浸开采前的淡化过程中溶浸矿体与注入淡水所发生的水岩反应，本文利用浸泡试验分析浸泡前后的水化学组分，通过逆向质量守恒模拟分析淡化过程中水岩反应机制。结果表明，砂岩型矿石蒸馏水浸泡过程中以盐岩溶解为主，硫酸盐、碳酸盐次之，硅酸盐溶解最少，说明该矿石淡化过程中由于矿物溶解，会释放出大量易溶离子，阻碍地下水淡化，其中蒸发盐岩是主要影响矿物。浸泡过程中浸出液总溶解固体(TDS)升高约1.27 g/L,模拟结果表明主要发生白云石、长石、石膏、盐岩和赤铁矿的溶解及白云母和方解石的沉淀，黏土矿物中高岭石、钙蒙脱石、伊利石均存在溶解的可能，沉淀以高岭石和钙蒙脱石为主，白云石与二氧化碳的溶解和方解石的沉淀使得溶液中重碳酸根离子浓度发生变化，长石与黏土矿物的溶解和云母的沉淀使得溶液中硅浓度发生变化。本研究可为识别地浸采铀发生的水岩反应和矿物沉淀堵塞提供技术支撑。     

低温核供热堆海水淡化装置的建模与仿真

为了研究山东核能海水淡化高技术产业化示范工程的系统最优运行方案和控制策略,建立能正确、全面反映其特性的数学模型是重要的先决条件之一。本文通过对系统的热力性能分析,建立了可用于低温核供热堆的热压缩多效蒸馏与反渗透混合法海水淡化的数学模型,并计算了系统在不同工况下的运行结果。通过与反渗透设备厂商软件计算结果及工程技术方案设计参数比较,结果表明,该模型可正确反映海水淡化系统运行特性,满足进一步研究的需要。     

只有核反应堆才能满足大规模海水淡化的需求

【美国《核子周刊》2005年3月24日刊报道】美国核学会(ANS)支持利用核能进行海水淡化,并认为只有核反应堆才能为大规模的海水淡化提供足够的能量。ANS在2005年3月下旬公布的一份声明中说,除非有新的海水淡化厂投入运行,否则到2025年将有超过18亿人生活在没有充足淡水供应的国家或地区。目前世界上已经进行了一些规模较小的核能海水淡化项目,累积运行经验超过150堆·年。但在全世界运行中的7500多座海水淡化厂中,绝大部分都使用化石燃料。ANS认为,从环境影响(例如温室气体)的角度来看,采用化石燃料是不能长久的,而可再生能源(例如太阳能…     

美国铀浓缩公司获得建设先导级联装置的许可证

【美国《核新闻》2004年4月刊报道】2004年2月,美国核管会(NRC)向美国铀浓缩公司(USEC)发放了在俄亥俄州派克顿(Piketon)的朴茨茅斯(Portsmouth)气体扩散厂厂址上建造和运营铀浓缩试验和示范装置的许可证。这座名为美国离心先导级联的装置将由240台实机规模的离心分离机组成,采用美国能源部(DOE)开发的离心技术。NRC表示,此次发放的许可证允许该装置在5年时间内处理和使用250 kg六氟化铀。USEC预计该示范装置将在2005年投入运行,工作人员数量将在50人左右。该示范装置将为商业规模铀浓缩厂的建设提供费用、进度和性能方面的数据。U…     

美核管会完成离心铀浓缩示范级联退役计划环境评价

正【世界核新闻网站2018年8月15日报道】美国核管会(NRC)已完成森图斯能源公司(Centrus Energy)提交的离心铀浓缩示范级联设施退役计划的最终环境评价,确认该设施的退役不会产生不可忽视的环境影响。这座设施位于俄亥俄州派克顿(Piketon)朴次茅斯(Portsmouth)气体扩散厂,旨在示范拟用于建设一座商业规模离心铀浓缩厂的气体离心机的性能。这座原型设施于2006年8月     

Seawater desalination plant using nuclear heating reactor coupled with MED process

A small size plant for seawater desalination using nuclear heating reactor coupled with MED process was developed by the Instituted of Nuclear Energy Technology,Tsinghua University,China,This seawater desalination plant was designed to supply potable water demand to some coastal or island where both fresh water and energy source are severely lacking ,It is also recommended as a demonstration and training facility for seawater desalination using nuclear energy. the desing of small size of seawater desalination plant couples two proven technologies:Nuclear Heating Reactor(NHR) and Multi-Effect Destination (MED) process.The NHR desing possesses intrinsic and passive safety features,which was demonstrated by the experiences of the project NHR-5.The intermediate circuit and steam circuit were designed as the safety barriers betewwn the NHR reactor and MED desalination system.Wihin 10-200MWt of the power range of the hating reactor,the desalination plant could provide 8000 to 150,000m^3/d of high quality potable water,The desing concept could provide 8000 to 150,000m^3/d of high quality potable water,The design concept and parameters,safety features and coupling scheme are presented.     

Modeling and simulation of cogeneration nuclear power plant for seawater desalination

Nuclear desalination of seawater remains a very viable option to solving the perennial fresh water shortage problem along the coast of Ghana especially as Ghana prepares to install the first nuclear power plant. There is, therefore, the need for research to be conducted into nuclear seawater desalination technology as part of the nuclear power program of Ghana so as to develop the needed human resources in Ghana. In this research, cycle analysis of the cogeneration nuclear power plant was conducted to determine its efficiency and desalination steam requirements. An analytical model of the thermo vapour compression (TVC) desalination process was also developed to investigate the effect of design and operating parameters on parameters controlling the cost of producing fresh water from TVC process. Steady state mass and energy balances as well as empirical correlations derived from experiments were used to model the TVC, which was coupled to a cogeneration nuclear power plant to supply the needed steam for the desalination. The model was developed on a computer code, using FORTRAN language. The results showed that the thermal performance of the TVC desalination process improves with the efficiency of the cogeneration nuclear power plant but decreases with increasing steam consumption rates.     

Development policy on new generation of nuclear power combined with desalination in China

The potential market for desalination industry is forecasted in China for a long term. A co-generation policy is proposed in power production and desalination. It has been predicted that the desalination would become a huge industry in China provided that the technology of desalination is improved and fresh water cost reduced to a certain Ievel accepted by Chinese residents.     

Sea-water desalination with nuclear and other energy sources: the EURODESAL project

This paper summarises our recent investigations undertaken as part of the EURODESAL project on nuclear desalination, currently being carried out by a consortium of four European, and one Canadian, industrials and two leading EU R&D organisations.Major achievements of the project, as discussed in this paper are:

• Coherent demonstration of the technical feasibility of nuclear desalination through the elaboration of coupling schemes for optimum cogeneration of electricity and water and by exploring the unique capabilities of the innovative nuclear reactors and desalination technologies.

• Verification that the integrated system design does not adversely affect nuclear reactor safety.

• Development of codes and methods for an objective economic assessment of the competitiveness and sustainability of proposed options through comparison, in European conditions, with fossil energy based systems.

Results obtained so far seem to be quite encouraging as regards the economical viability of nuclear desalination options.Thus, for example, specific desalination costs ($/m³ of desalted water) for nuclear systems, such as the AP-600 and the French PWR-900 (reference base case), coupled to multiple effect distillation (MED) or the reverse osmosis (RO) processes, are 30–60% lower than the desalination costs for fossil energy based systems, using pulverised coal and natural gas with combined cycle, at low discount rates and recommended fossil fuel prices. Even in the most unfavourable scenarios for nuclear energy (discount rate=10%, low fossil fuel costs) desalination costs with the nuclear reactors are 7–20% lower, depending upon the desalination capacities. Furthermore, with the advanced coupling schemes, utilising waste heat from nuclear reactors, the gains in specific desalination costs of nuclear systems are increased by another 2–15%, even without system and design optimisation. A preliminary evaluation shows that desalination costs with the GT-MHR, coupled to a MED process, could still be much lower than the above nuclear options for desalting capacities≤43 000 m³ per day. This is because its design intrinsically provides “virtually free” heat at ideal temperatures for desalination (80–100 °C).     

200MW核供热堆核能海水淡化及接口方案的研究

简要介绍了核能海水淡化的必要性以及２００ＭＷ核供热堆的技术安全特点，并从该堆的特点出发，探讨了它与海水淡化厂的１４种接口方案，通过经济、技术及安全性方面的分析比较，从中选取了适合２００ＭＷ核供热堆的较为理想的接口方案为：蒸汽发生器＋ＭＥＤ海水淡化厂（单一产水方案）和蒸汽发生器＋汽轮发电机组＋ＭＥＤ海水淡化厂（水电联产方案）。     

核电站信息数据库应用现状及其探讨

本文从核电站信息数据库对核电站运行安全的作用入手,分析了国内外核电站信息数据库的应用现状,对国内核电站信息数据库的发展类别进行了讨论,并探讨了我国核电信息数据库建造的发展条件与存在的问题。     

AP1000型核电机组运行期间的预期氚排放

AP1000型核电机组电站放射性废物处理的特点决定了其预期氚排放总量可能高于同功率水平的传统压水堆核电站。在AP1000机组正常运行期间,除了需要加强氚排放的环境监测,更重要的是从源头优化管理和控制氚排放,最大限度地减少氚排放对环境的影响,保障环境安全和公众健康。本文简要介绍了压水堆中氚的产生,详细分析了AP1000机组液态和气载氚的产生和排放机制,给出了采用保守和优化方法计算的AP1000机组的预期氚排放量,讨论了AP1000机组氚排放量最小化的优化控制措施。无论单机组还是6机组厂址,AP1000堆型核电站氚预期排放量都满足我国相关标准限值的要求。     

铅铋合金系统氧控旁路性能数值研究

为研究通过固态氧控有效调节铅铋合金（LBE）系统氧浓度的方法,本文通过修正液态LBE腐蚀经验公式,结合氧化铅（PbO）溶解模型,基于集总参数法并使用FORTRAN语言自编程序计算LBE系统氧浓度;据此研究主回路流量、质量交换器（MX）内温度、PbO装量对自主设计的小型LBE系统的MX供氧性能的影响;初步建立MX设计准则,获得一定约束条件下MX供氧性能及其氧控旁路设计参数。本研究可为LBE系统氧控旁路的设计和计算提供参考,同时提供一种高效求解LBE系统瞬态氧浓度和腐蚀的计算方法,为建立氧浓度模型预测系统提供新思路。