AP1000核电站~(106)Ru正常运行源项研究

AP1000核电站一回路中~(106)Ru的现实源项远远高于其设计源项,其一回路活度浓度与131I相当,既从理论计算分析不可信,又与电厂实际测量数据不符。一回路~(106)Ru活度浓度过高,使得电厂液态流出物中106Ru及其子体~(106)Rh占到除氚和碳-14外放射性年排放量预期值的一半以上,严重背离电厂运行经验,而且对AP1000电厂流出物监测、环境监测和环境影响评价造成了误导。本文分析了ANSI/ANS-18.1中现实源项计算方法存在的问题,研究提出了从一回路主要核素活度浓度出发计算~(106)Ru现实源项的方法,其计算结果与M310/CPR1000、VVER-1000等国内压水堆电厂的现实源项基本一致,能客观反映压水堆电厂~(106)Ru源项,可供国内AP1000核电厂源项计算时参考。     

电流模式下微型裂变电离室参数对探测性能的影响

裂变电离室在工作时,其内部气体中持续地发生着电离和复合过程。为了进一步了解这些过程对探测性能的影响,需要从等离子体物理的角度来研究裂变电离室。借助BOLSIG+以及电流模式下微型裂变电离室的基本理论模型,计算了电极的几何尺寸、裂变率以及气体电离度等参数对探测器饱和区电压范围的影响,并对结果进行了讨论。此外,根据不同电离度情况下的计算结果,对高温导致探测器饱和区电压范围变小这一现象给出了一种可能的解释。     

PIXE analysis and fission track dating of obsidian from South American prehispanic cultures (Colombia, Ecuador)

In the present work we have coupled PIXE with fission track dating to characterise obsidian artefacts from about 40 archaeological sites of Colombia and Ecuador. PIXE analysis, carried out with the external beam line of the AGLAE tandem accelerator, yields the content in about 15 elements with Z > 8, whereas fission track dating is applied to ages in excess of about 10 000 years. About 120 artefacts were investigated by PIXE, of which 50 were dated by fission tracks. Ages and compositions were compared to those of obsidians from all known geological sources of the region. We show that this double characterisation allows us to determine the number of obsidian sources exploited in an ancient past and to give some insight into obsidian circulation.     

Percolation on grain boundary networks: Application to fission gas release in nuclear fuels

The percolation behavior of grain boundary networks is characterized in two- and three-dimensional lattices with circular macroscale cross-sections that correspond to nuclear fuel elements. The percolation of gas bubbles on grain boundaries, and the subsequent percolation of grain boundary networks is the primary mechanism of fission gas release from nuclear fuels. Both radial cracks and radial gradients in grain boundary property distributions are correlated with the fraction of grain boundaries vented to the free surfaces. Our results show that cracks surprisingly do not significantly increase the percolation of uniform grain boundary networks. However, for networks with radial gradients in boundary properties, the cracks can considerably raise the vented grain boundary content.     

Analysis of the FIC detector data at the n_TOF facility

Fission cross-section measurements with the Fast Ionization Chamber (FIC) at the CERN n_TOF facility were challenged by intense signals due to γ-rays and ultra-relativistic particles from the impact of the 20 GeV proton pulses on the neutron spallation target. A method for analyzing the data taken with Flash Analog to Digital Converters (FADC) was developed to treat these problems in an automated way to provide a reliable background subtraction and a fit routine for identifying fission events even at high energies. The analysis is illustrated at the example of the fission cross-section of ²³⁸U relative to that of ²³⁵U in the energy range from 40 keV to 300 MeV.     

Point by Point model calculation of the prompt neutron multiplicity distribution P(ν) for spontaneous and neutron induced fission of actinides

The prompt neutron multiplicity distribution P(ν) is a very sensitive quantity which depends on the model calculation of the multi-parametric matrix ν(A,TKE) and on the fission fragment distributions.     

严重事故下裂变产物气溶胶自然沉积现象研究

以600 MW压水堆核电厂为研究对象,在一体化安全分析模型的基础上建立重力沉降、扩散电泳、惯性碰撞和热电泳4种裂变产物气溶胶的自然沉积模型,选取典型的严重事故序列,分析严重事故下裂变产物气溶胶的自然沉积现象。将MELCOR程序的重力沉降模型植入本文的一体化分析模型,对重力沉降份额进行比较。研究表明,重力沉降对气溶胶沉积的贡献最大;本文采用的重力沉降模型比MELCOR程序重力沉降模型的沉降效应稍强。     

机床夹具结构设计及方案构思原则

结合生产实践,应用一些简单实用图例,由多个方面说明机床夹具零部件设计中结构设计及方案构思的要点和技巧,供技术人员在解决实际问题时参考.     

Models for the release from fuel of Ce, La, Sr, and Eu in accident conditions

During a hypothetical severe nuclear accident involving a pressurised water reactor, it is of primary importance to assess the potential radionuclide releases into the environment. With that view in mind, analytical models have been developed for the release kinetics from fuel of four low-volatile fission products (namely cerium, lanthanum, strontium, and europium) in severe accident conditions. The vaporisation of those fission products from fuel has been evaluated by means of thermodynamic equilibrium calculations. The effects of the fuel temperature and the oxygen potential on the chemical form and volatility of the fission products have been determined. Finally, these models have been integrated in the ASTEC and have been subsequently validated against annealing experiments with various oxidizing and reducing conditions.