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.     

滴流床设计放大中的重要参数及其数学模型

讨论了在滴流床放大过程中必须加以考虑的重要物理和化学因素以及这些因素对设计放大的影响．介绍了确定这些参数的原理和方法，推荐了用于计算这些参数的关系式，列举了用于不同反应系统的数学模型，比较了模型预测值与实验值．     

宝钢马迹山港供电系统无功补偿分析

针对宝钢马迹山港原供电系统功率因数低下的问题，提出了一种新的无功补偿容量计算方法。此方法结合TCR FC的补偿方案，成功实现了该供电系统在冲击性负荷下功率因数大于0．9的目标。     

产氚聚变堆概念设计系统研究

提出了基于球环类型的先进氚生产堆概念设计,它是聚变能发展的中间应用。与传统托卡马克氚生产堆不同,设计中利用了球形环的先进等离子体物理性能和紧凑的结构特征,并尽量利用真空室内的空间安置氚生产包层以减少氚泄露而增加氚增殖率,达到年生产氚1000 g的目标,相应的堆利用因子为40％。在2D中子学计算的基础上提出了较为完整的初步概念设计。逐项进行了分析,同时对设计的风险、不确定性和后备方案也做了概括的解释。为下一步更详细、具体的概念设计提供了直接的依据和重要的参考价值。     

Neutronic performance of new coolants in a fusion–fission (hybrid) reactor

Selection of coolant used in the fuel zone of a fusion–fission (hybrid) reactor affects the neutronic performance of the blanket much. Recently, two coolants namely, Flinabe and Li₂₀Sn₈₀ have been investigated to use in fusion reactors as tritium breeder and energy carrier due to their advantages of low melting point, low vapor pressure. In this study, neutronic performance of these coolants in a hybrid reactor using Canada Deuterium Uranium Reactor (CANDU) spent fuel was investigated for an operation period of 48 months. And also that of natural lithium and Flibe was also examined for comparison. Neutron transport calculations were conducted on a simple experimental hybrid blanket in a cylindrical geometry with the help of the SCALE4.3 system by solving the Boltzmann transport equation with the XSDRNPM code in 238 neutron groups and a S₈–P₃ approximation.     

Power Flattening in ARIES-RS Fusion Breeder Reactor Using Mixed Fuels

This study presents the possibility of the power flattening in the ARIES-RS breeder reactor using mixed (Th,U)C or (Th,U)N fuels. Two different types of mixing, namely, homogeneous mixing (HM) and linear mixing (LM) were used to investigate the uniformity of fission power distribution through the fuel zone. In HM, fraction of uranium content were kept constant in all rows of the fuel zone whereas, in LM the fraction of the uranium were linearly increased from the first to last fuel row in the fuel zone. Neutron transport calculations were performed with the aid of the SCALE4.3 system by solving the Boltzmann transport equation with the XSDRNPM code in 238 neutron groups and a S₈–P₃ approximation. Flat fission power distribution was maintained successfully for the blanket using linearly mixed fuels. However, the fission density profile was not uniform in the blanket with homogeneously mixed fuels. It decreased exponentially form the 1st to 10th fuel row.