Modeling and Simulation for PWR Rressurizer Based on Modelica

稳压器是压水堆核电站的重要设备之一。使用面向对象的建模工具Modelica/Open Modelica仿真软件对稳压器进行新模型的开发,并将模型仿真结果与希平港核电站减负荷试验结果进行比较,验证新建模型的有效性,可为核电站其它系统设备的建模仿真的应用提供参考。Modelica语言对象导向的特性为核电站系统设备全生命周期的模型开发实现继承和延伸管理。Pressurizer is one of the important equipment in the pressurized water reactor nuclear power plant. Using oriented object modeling tool Modelica/Open Modelica simulation software, the new model of Presssurizer was developed, and simulation results and Shippingport nuclear power plant loss load test results were compared and the validity of the new model was verified. It can provide a reference for the application of the modeling and simulation of other system and equipment in the nuclear power plant. Modelica language object oriented characteristics can achieve the inheritance and extension management of nuclear power plant system and equipment modeling development for the whole life cycle

CPR1000全厂断电叠加小破口事故下一回路外部注水策略分析

严重事故管理导则(SAMGs)是目前缓解核电站严重事故进程的主要依据,而对反应堆一回路进行卸压和补水是严重事故下保证堆芯冷却最常用的策略,但是目前的SAMGs对于外部注水策略并没有给出具体的操作指导。所以,本研究以我国目前广泛应用的CPR1000核电站作为研究对象,以全厂断电叠加小破口事故作为基础事故序列,采用模块化严重事故分析程序对其进行建模,并对一回路外部注水策略进行了详细分析。结果表明,根据不同外部注水时间采取合适的卸压速率及注水流量可有效缓解事故进程,使堆芯冷却,防止压力容器失效,大量放射性外泄。该研究成果可为完善CPR1000核电站SAMGs中外部注水的具体措施以及核电厂类似序列的培训课程提供参考。厦门大学能源学院发展基金(2017NYFZ01

Growth and Decline and Balance of Organic Matter in Newly Built Loessal Soil Farmland in Ansai County

通过对新修黄绵土农地有机质的田间定位与尼龙袋模拟试验研究得出：（１）新修黄绵土农地，增加施肥量，尤其是有机肥用量，是提高陕北丘陵沟壑区土壤有机质的主要途径；（２）作物根茬腐殖化系数除与生物气候条件有关外，与本身化学组成关系密切。四种作物根茬腐殖化系数为：糜子根茬＞黄豆根茬＞谷子根茬＞养麦根茬；（３）原土壤中有机质矿质化系数，以休闲地采用化学动力学一级反应方程求得的数据较稳定，并接近大田实际情况；（４）利用有机质平衡定量施肥模式，可算出在陕北黄绵土区要达到土壤有机质培肥目标的有机肥用量

Study on low carbon ammonia engine

化石燃料的过度使用引发了一系列能源和环境问题,氨作为可再生环保燃料可有力缓解石油资源短缺的现状和改善大气环境。文章试验研究了氨气/液化气混合燃料发电机的性能和低碳处理效果。在改造汽油、液化气双燃料发电机组的基础上,研究了混合燃料中氨百分比逐渐增大时发动机性能的变化以及氨水装置对尾气的净化效果。研究结果表明,氨气/液化气混合燃料发电机在一定程度上可以保持其负载性能,氨气比例增加到一定值时,发电机的输出功率和电压会逐渐下降;氨发动机的尾气经过氨水装置后,二氧化碳的浓度可以降低到1%左右,实现低碳排放。Overuse of fossil fuel has caused a series of energy and environmental problems.However,ammonia is a kind of renewable and environment-friendly fuel and it can greatly relieve shortage of petroleum resources and improve atmospheric environment.Study on performance of generator that runs on ammonia/LPG mixture fuel and its low carbon emission is put forward in this paper.The influence of various percent of ammonia and LPG mixture on engine performance is studied and the effect of ammonium hydroxide purification for emission reduction is investigated based on a reformed Gasoline/LPG dual fuel generator set.Experimental results showed that the engine with load could maintain its dynamic performance when the proportion of ammonia was small, however, as the proportion of ammonia increased to some extent, the generator power and voltage would decrease;meanwhile, the percentage of carbon dioxide would reduce to 1% when the engine emission was ventilated into ammonium hydroxide device, in this way the engine carbon emission was low.福建省科技厅平台项目(2007H2002); 福建省科技计划项目(2013I0007

Radioactive Simulation Study of PWR System Loop Based on 3Keymaster Platform

核电站一、二回路放射性水平的分析和仿真,是实现核电站辐射监测系统仿真的重要组成部分。本文对放射性源项进行分析和简化、建立核素释放和输运模型,并基于3Keymaster仿真平台对一、二回路的放射性水平进行仿真。给出在SGTR、燃料棒破损事故条件下的系统回路内的放射性仿真结果,以验证放射性核素释放及输运模型的合理性和适用性。The analysis and simulation of the primary and secondary loop radioactive level at nuclear power plant plays an important role in achieving radiation monitoring system simulation.It has been presented in this paper the nuclear power plant radioactive source term analysis and simplification,the source term release and transport model establishment,and the primary and secondary loops radioactive levels simulation based on 3Keymaster simulation platform.The paper has also given the simulation results under SGTR and fuel rods damaged accidents conditions to verify the reasonableness and suitability of the radionuclide release and transport models.福建省科学技术厅重点项目“事故工况下核电站辐射监测仿真研究”(2013I0007

CPR1000全厂断电叠加小破口失水事故下一回路外部注水策略分析

严重事故管理导则(SAMGs)是目前缓解核电站严重事故进程的主要依据,而对反应堆一回路进行卸压和注水是严重事故下保证堆芯冷却最常用的策略,但是目前的SAMGs对于外部注水策略并没有给出具体的操作指导.为此,以我国目前广泛应用的CPR1000核电站作为研究对象,以全厂断电叠加小破口失水事故作为基础事故序列,采用模块化严重事故分析程序对其进行建模,并对一回路外部注水策略进行了详细分析.结果表明,根据不同外部注水时间采取合适的卸压速率及注水流量可有效缓解事故进程,使堆芯冷却,防止压力容器失效及大量放射性物质外泄.该研究成果可为完善CPR1000核电站SAMGs中外部注水的具体措施以及核电厂类似事故序列的培训课程提供参考.厦门大学能源学院发展基金（2017NYFZ01

The framework of nuclear management information system

Conference Name:2011 International Conference on Web Information Systems and Mining, WISM 2011. Conference Address: Taiyuan, China. Time:September 23, 2011 - September 25, 2011.Taiyuan University of TechnologyAs known to all, building nuclear power plants has the characteristics of large investment, long cycle, technical difficulties, too many interfaces and complex management and coordination, so the application of computer can help improving project management, improving work efficiency and quality, as well as cost reduction, wealthy information accumulation and enhancing the nuclear power enterprise market competitiveness. Nuclear power Management Information System (MIS) is a typical representative of this application. In this paper, taking the demand for document management, information search and real-time communication into consideration, we propose a solution and a framwork for development by using of SharePoint, RMS, Autonomy, exchange, Office Communication Server (OCS). ? 2011 Springer-Verlag