设计S—N曲线的概率估计和ASME法的可靠性评价

基于ＬａｎｇｅｒＳ－Ｎ曲线,提出了设计Ｓ－Ｎ曲线的概率估计方法和ＡＳＭＥ法的可靠性评价方法。Ｐ－Ｓ－Ｎ曲线由文中提出的广义极大似然法估计。方法可应用于处理具有双随机性特征的Ｓ－Ｎ数据,并可推广应用于处理应力控制成组法疲劳试验和极大似然法试验得到的Ｓ－Ｎ数据。     

PSA通用数据库中超参数的估计方法研究

在构建核电厂概率安全评价可靠性通用数据库时,通常难以确定核电设备的超参数值.如果超参数的值不准确,那么堆芯损伤频率的不确定性分析结果将受到影响,而且也难以开展设备可靠性参数的贝叶斯更新.为解决这方面问题,根据经验贝叶斯方法,研究从设备失效记录得到可靠性通用数据过程中的统计学模型和参数估计方法,重点讨论矩法估计和极大似然法估计的数学原理,并通过举例介绍这两种方法的实际应用.     

16MnR钢焊接头概率循环应变-寿命模型的综合分析

对16MnR钢焊接头概率循环应变一寿命模型作了综合分析。综合利用不同试验条件下的试验数据,提出了合理的材料与结构概率设计分析曲线。模型用概率三参数幂指数模型表征,同时考虑了试验数据分散性和样本量对概率评价的影响,包含了存活概率曲线、置信度曲线和两者融合曲线,可为工程实践提供广泛的选择性。作为比较,相应给出了16MnR钢母材的各曲线参量。     

三模式氡测量刻度装置的研制

为满足实验室对一般氡测量仪器的刻度需要,设计了能够实现在脉冲模式、恒定模式和连续模式三种模式下自动控制、自动监测的氡测量刻度装置,并对装置进行了稳定性和可靠性试验。试验结果表明,该装置可为氡及其子体的研究以及其测量仪器的标定提供一个可调节、具有稳定氡浓度的环境。     

常用4对剂量学量的主要区别和相互关联

在电离辐射技术的所有应用领域,几乎都需要用到辐射剂量学量。此文专门评述常用4对剂量学量(照射量与照射量率、吸收剂量与吸收剂量率、比释动能与比释动能率、比转换能与比转换能率)的主要特点、彼此区别和相互关联等。显然,实际工作中准确理解并正确使用这4对常用剂量学量至关重要。     

用于中能重离子碰撞研究的三套Phoswich

本文介绍了三套由１ｍｍ的ＰＩＬＯＴ Ｕ型快塑料闪烁体和４０ｍｍ的ＮＥ１１５慢塑料闪烁体组成的Ｐｈｏｓｗｉｃｈ。用＾６０Ｃｏγ射线测得探测器的时间分辨为４００ｐｓ。Ｐｈｏｓｗｉｃｈ测到的粒子能量范围也进行了计算。     

有限数据下结构疲劳可靠性设计曲线的统计模型

提出了有限数据下确定反应堆结构疲劳可靠性设计S－N曲线的统计模型,该模型置信度－存活率概率－强度－寿命（C－P－S－N）曲线来表示考虑了常规P－S－N曲线预测结果的可信性,应用线性回归统计分析原理,将置信度引入到常规P－S－N曲线中,从而得到C－P－S－N曲线。1Cr18Ni9Ti不锈钢管道焊接缝金属材料试验数据分析结果说明了模型的合理性和可用性,同时还说明了有限数据下常规P－S－N曲线偏于危险。     

Design of a TE10 Taper Used in the LHCD Launcher for EAST

Calculations of the TE10 tapered waveguide, which will be used in the 4.6 GHz lower hybrid current drive （LHCD） launcher on the EAST, are presented. The calculations are performed in two ways, namely by directly solving the classical coupling wave equations, and by using the simulation code of the high frequency structure simulator （HFSS）. According to the calculations, the voltage standing wave ratio （VSWR） of the designed tapered waveguide can be less than 1.01 within a bandwidth of ±100 MHz.     

AC—600反应堆压力容器设计探讨

本文根据 ALWR 的基本设计原则,初步分析了我国 AC-600反应堆压力容器的设计特点,探讨了保证 AC-600反应堆压力容器的可靠性应采取的主要技术措施.     

Probabilistic model for the economic evaluation of nuclear projects

In this article a probabilistic model for the economic evaluation of nuclear power plants was developed. It was focused on modeling the potential risks associated to financial, safety and institutional aspects involved in the reactor construction schedule. The probabilistic results have shown a wide spread on the economic performance due to the schedule complexity and coupling of tasks. This spread increases exponentially to the discount rate, and hence, becomes more important for developing countries. Moreover, the probabilistic assessment—rather than classical approach—seems to be the right choice in order to take into account coupled uncertainties relevant on nuclear projects.     

Evaluation of Computational Models for Fission and Spallation Reactions Used in Accelerator Breeding and Transmutation Analysis Code

Computational models for spallation and fission reactions used in an accelerator breeding and transmutation code have been evaluated by performing calculations for thin targets of Bi, Pb, Th and U in the energy range of 50–1,000 MeV. Proton and neutron non-elastic and fission cross sections have been derived from the counts of real collisions and fission events in the targets.

Several fission models in combination with a spallation model are compared with the experimental data due to Steiner et al. and Schimmerling et al. A good agreement has been obtained for a model with the level density parameters a_n = A/10 and a_f/a_n fitted to the data due to Il'inov et al. The mass dependence of the non-elastic cross sections has been calculated also with the use of the best fit model. A good agreement with the experimental data was obtained over a wide range of nuclear masses.     

Creation and Development of Computational Methods for Estimating the Strength of Equipment and Pipes Used in Radiochemical Production Processes at the Industrial Association Mayak

The Industrial Association Mayak chose for computations to substantiate the safety of equipment used in radiochemical production processes domestic computer codes, which are as good as the foreign codes but also have an important advantage over the latter – they are tied to the Russian standards.Some of the most typical types of radiochemical industrial equipment in whose design strength calculations were performed using the universal CAN system and the TsIKL code, developed at the ITsP of the Ministry of Atomic Energy, are presented. The computational examples show that the programs indicated make it possible to perform a standardized estimate of the strength of equipment and pipes with any degree of complexity which are used in radiochemical production processes at the Industrial Association Mayak.