Transient pressure analysis for the reactor core and containment of a HTGR after a primary loop pressure boundary break accident

The pressure variances in the reactor core and containment of a High Temperature Gas-cooled Reactor (HTGR) after a primary loop pressure boundary break accident determine the structural integrity and safety of the reactor. Based on mass conservation, energy conservation and state equations, explicit formulae for the transient pressure and temperature variances in the pressure vessels were deduced, and a set of differential equations for the transient pressure and temperature variances in the containment were developed. Numerical simulation was also conducted to investigate the transient pressure and temperature variances in the pressure vessels and containment. The results show that energy transformation due to expansion work cannot be neglected. The maximum pressure in the containment could increase by 40 percent due to blockage caused by air in the containment. Detailed numerical simulations of the transient pressure and temperature variance in the reactor core flow passages were also conducted. The results show that the pressures acting on the reactor core and containment are below acceptable values.     

A brief introduction to neutron activation analysis in China

The history, the major achievements in both methodology and applications, the current trends and future perspectives of neutron activation analysis (NAA) in China are briefly described.     

SCWR for Future LargeScale Nuclear Power Generation

The ambitious nuclear power program motivates the Chinese nuclear community to develop advanced reactor concepts of generation IV, in order to ensure the longterm, stable and sustainable development of nuclear power. The supercritical watercooled reactor (SCWR) has favorable features in economics, sustainability and technology availability. It is the logical extension of the existing PWR technology and has very promising perspectives in largescale power generation in China. This paper describes the main features of SCWR. New designs of SCWR core structure and fuel assemblies are proposed. Preliminary analysis using a coupled neutronphysics/thermalhydraulics method is carried out and shows a good feasibility of the new design proposal.     

乏风瓦斯热逆流反应器的流动压力损失特性

分析了热逆流反应器压力损失的组成和机理,上下集气箱内和陶瓷床内部的摩擦阻力损失和陶瓷床进出口的局部损失,建立了各部分压力损失的相应公式并根据实验数据进行了计算.结果表明:陶瓷床进出口的局部流动损失远小于摩擦阻力损失,因此可以在损失分析时忽略以使问题简化;下集气箱中的摩擦阻力损失明显大于上集气箱和陶瓷床,并且对进口流速的增长最为敏感,在总损失中占据首位;给出了热逆流反应器的总压力损失计算公式,应用该式可对不同流量工况下的总损失进行计算.     

IC厌氧反应器处理马铃薯淀粉废水特征研究

采用IC(厌氧内循环)法,通过自行研制的IC反应器,研究了马铃薯淀粉废水处理效果,结果表明:初次启动历时25 d,二次启动仅仅历时6d,COD去除率均可保持在80％以上;反应器所能耐受的最大有积负荷为40.57 kg COD/(m3·d);最经济有效的停留时间为5h,最佳负荷为28.75 kg COD/(m3·d).     

CuZnAl双功能催化剂上一步法合成二甲醚的工艺研究

探讨TC301／γ-Al2O3和C207／γ-Al2O3双功能催化剂上合成气一步法制取二甲醚的反应,考察了催化剂浓度、原料气氢碳比和搅拌转速对一氧化碳转化率和二甲醚收率的影响．结果表明：在浆态床反应器内,催化剂C301的催化效果优于C207,且催化剂最佳浓度为7．27％;在300r／min搅拌转速下,外扩散阻力的影响基本可以消除;当原料气氢碳比为1．0时,二甲醚收率最大,进而提出利用富碳合成气生产二甲醚是缓解能源问题和减少能源污染的一条新途径．     

生物质热解研究进展(综述)

从生物质能的转换方式出发,主要介绍了热解反应器、快速热解、催化热解、影响因素、热解产物等研究现状,分析了生物质主要成分的热解机理,指出了这些技术中需要解决的问题以及目前的主要研究方向。     

气升式环流反应器内气液两相流动计算流体力学的模拟

采用欧拉-欧拉两流体模型模拟了气升式环流反应器内部气液两相流动过程,考察了液相速度和气含率随表观气速的变化,液相速度和气含率模拟值的关系与两种经验关系式的计算值进行了比较,两者取得了很好的一致,证明了模型的正确性。在此基础上,使用计算流体力学模拟的方法考查了反应器内的导流筒直径和导流筒高度对反应器内两相流动的影响,导流筒直径增大,液相循环量增大,上升段气含率增大;导流筒位置升高,液相循环速度和循环量均增大,上升段气含率减小。所获得的结果对气升式反应器的设计优化具有指导意义。     

三相淤浆床中合成气直接合成二甲醚双功能混合催化剂的失活研究

用双功能混合催化剂在三相淤浆床反应器中进行合成气直接合成二甲醚,考察双功能混合催化剂在三相床中的稳定性和失活现象。探讨了合成气含水蒸气对合成二甲醚以及合成甲醇的影响。分析了三相淤浆床反应器中直接合成二甲醚催化剂的失活原因,认为反应中生成的水是催化剂活性降低的原因之一。氨的程序升温脱附、X射线衍射、X光电子能谱表征结果证实甲醇合成催化剂中活性组分Cu晶粒的长大及甲醇合成催化剂中Cu元素流失导致双功能催化剂活性降低。     

裂解汽油加氢脱噻吩中二段反应器入口温度的影响

以工业生产的实际数据对实验关联的噻吩加氢脱硫表观反应动力学方程加以修正,得出反应动力学方程:r=6.935×1-0 12exp-45 054RTp1.H 42p0.T h83。研究了等温条件下温度对噻吩加氢的影响,并对二段反应器中实际温度的测定曲线进行了模拟比较。结果表明:温度是噻吩脱除反应的关键因素,入口温度应随着床层绝热温升的下降而逐步提高。