Application of advanced core process monitoring procedures in German power reactors

The nuclear reactor core design and the nuclear fuel management have been changed remarkable during the last few years. This development was initiated by increasing costs for the fuel recycling and nuclear waste storage. The fuel material, the fuel pellet fabrication, the fuel assembly structure and the core composition have been varied to get an effective fuel exploitation. Based on advanced core process conditions the reactor power and the fuel burn-up have been increased at German plants in recent years. Improved dynamic process monitoring procedures are required to get more information about the varied core process behaviour during the reactor operation. Since several years ISTec has been performed investigations to the process monitoring based on process signal measurements in German nuclear power plants. Using the standard instrumentation of the plants process signals have been measured and analysed by means of the digital data acquisition system SIGMA. The measured time signals are influenced by core process transients, global and local process fluctuations and by signal line transfer functions. Advanced time series analysis methods have been applied to separate different process effects in the multiple signal matrix. The separation of different process influences can improve significantly the information about the process condition in the reactor core.     

中国先进研究堆冷中子导管的模拟研究

应用蒙特卡罗方法对中国先进研究堆(CARR)上的两条冷中子导管CNG1和CNG2的设计方案进行了模拟研究。在假定的冷中子源谱分布下,两条导管出口处的中子注量率均达到1×109cm-2·s-1以上。CNG1和CNG2的中子传输效率分别为50%和42%,中子束最大发散角分别为2 2°和1 9°。中子束沿水平方向的分布均匀,其最大起伏不超过3%。重力显著影响中子束沿垂直方向的分布。     

安全分析程序SAC-PREARS的开发

介绍了SAC-PREARS程序的基本数学模型。利用MISAP程序和通用程序TRAC-PFI对SAC-PREARS计算结果进行了验证。结果表明：SAC-PREARS程序能够有效地计算和分析核供热堆PRHRS的稳态和瞬态热工水力特性。     

岷江试验堆Q15孔道中子谱测量试验的研究

为了确定岷江试验堆(简称MJTR)堆芯铍反射层内中子能量E >1.0MeV的快中子注量率,采用一组中子探测片测量了岷江试验堆内第一层铍反射层外Q15孔道内的快中子注量率谱,并由测量谱求得各阈能探测片的快中子反应的谱平均截面和该孔道测量点位置的快中子注量率。结果表明,铍反射层内快中子(E>1.0MeV)注量率为1.985×1012 cm-2·s-1,MJTR每运行一段,铍反射层内快中子(E>1.0MeV)积分注量最大可达1.54×1018cm-2。通过本次试验研究,为更好的开发利用MJTR提供了试验依据。     

堆泵浦3He-Ar-Xe激光体系小信号增益与效率实验研究

介绍了CFBR-Ⅱ堆泵浦3He-Ar-Xe体系1.73μm波长激光小信号增益和泵浦效率的实验研究.在脉冲峰热中子注量率为6.9×1014cm-2.s-1、3He、Ar、Xe气体的比例为80.219.30.5,总压强为8.3×104Pa时,采用透射率从1.7%到10%的6个谐振腔输出镜均获得了激光输出.在谐振腔输出镜透射率为7%时,得到了激光脉冲峰功率为45mW,其对应的激光泵浦效率为1%.在此基础上,利用Rigroa分析方法拟合出3He-Ar-Xe体系激光的小信号增益为0.24%/cm,饱和光强为36W/cm2.     

周期性脉冲流体对滴流床反应器性能的影响

用铜铬催化剂催化的过氧化氢分解反应作为液体限制反应的例子来研究周期性脉冲流体对滴流床反应器性能的影响.初步研究表明:当催化剂非完全润湿时,周期性脉冲流体能够提高反应器的性能;当催化剂完全润湿时,周期性脉冲流体不能提高反应器的性能,甚至还会产生不利影响.     

铅冷快增殖堆物理和热工水力研究

对25MW电功率铅冷快增殖堆堆芯进行了物理和热工水力概算，并将计算结果与相同功率的钠冷快增殖堆的结果进行了分析比较。从初步概算的结果来看，铅冷快增殖堆是一种安全可行的快增殖堆堆型。     

ATHLET 程序及其在低温供热堆中的应用

ATHLET 程序是德国核设施安全评审中心GRS开发的一个重要的反应堆热工水力学分析程序.它可分析除堆芯熔化事故之外的其他设计基准事故,可应用于美欧传统和先进的压水堆和沸水堆,原苏联设计的压水堆(VVER)和石墨水冷堆(RBMK),以及加拿大的CANDU堆等反应堆系统的热工分析.介绍了微机版ATHLET程序,并用它对5 MW低温供热堆自然循环稳态运行工况进行了计算,结果和试验数据符合很好.     

Flow Simulation and Optimization of Plasma Reactors for Coal Gasification

This paper reports a 3-d numerical simulation system to analyze the complicated flow in plasma reactors for coal gasification, which involve complex chemical reaction, two-phase flow and plasma effect. On the basis of analytic results, the distribution of the density, tempera-ture and components‘ concentration are obtained and a different plasma reactor configuration is proposed to optimize the flow parameters. The numerical simulation results show an improved conversion ratio of the coal gasification. Different kinds of chemical reaction models are used to simulate the complex flow inside the reactor. It can be concluded that the numerical simulation system can be very useful for the design and optimization of the plasma reactor.     

三相电压型低谐波PWM整流器主电路参数间的关系

三相电压型低谐波PWM整流器主电路的多个参数之间的关系较为复杂，在仿真和实验中，若给出的参数不合理，则变换器不能正常工作，从而给仿真和实验带来一定困难。文章在考虑了输入电阻的情况下，给出了功率因数角为任意值时，主电路各参数和控制参数间的稳态关系及一些参数的约束关系。上述关系对于分析和设计被研究电路具有很好的指导意义，文中的公式通过了仿真验证。