如何根据ASME规范产品RT标记确定焊接接头系数

用焊接方法建造的ASME规范产品,其焊接接头系数与焊接接头的无损检测程度密切相关。在ASME规范压力容器卷中明确规定了焊接接头系数选取规则,但在一些较为复杂的情况下却很容易引起误解而选错系数。通过详细分析ASME规范中关于RT标记的要求和应用,探讨在实际应用中如何根据产品的RT标记来确定焊接接头系数。     

2004版ASME锅炉和压力容器法规第Ⅱ卷A篇主要变动情况探析

对2 0 0 4版ASME锅炉和压力容器法规(ASME法规)第Ⅱ卷A篇的主要变动情况做了归纳总结和分析,介绍了新材料纳入ASME法规,以及法规中对铬钼钢回火脆性倾向的评定和试验规定,并列出了2 0 0 4版ASME法规第Ⅱ卷A篇的主要变动情况。     

核电厂在役检查技术验证方法对比

以基于ASME规范的验证方法和ENIQ验证方法为对象,讨论2种在役检查技术验证方法的特点及其各自存在的问题。ASME规范要求的验证方法侧重于某一类部件检测技术的验证,强调盲测试验和判定验证的统计学证据的重要性;对于某些特定部件检测技术的验证,ASME规范XI卷附录Ⅷ中的相关规定不够明确。ENIQ验证方法强调通过技术论证和实际测试的结合进行验证,适应性较强。通过比较2种验证方法的特点,对我国的在役检查技术验证提出建议。     

Modeled salt density for nuclear material estimation in the treatment of spent nuclear fuel

Spent metallic nuclear fuel is being treated in a pyrometallurgical process that includes electrorefining the uranium metal in molten eutectic LiCl-KCl as the supporting electrolyte. We report a model for determining the density of the molten salt. Material balances account for the net mass of salt and for the mass of actinides present. It was necessary to know the molten salt density, but difficult to measure. It was also decided to model the salt density for the initial treatment operations. The model assumes that volumes are additive for the ideal molten salt solution as a starting point; subsequently, a correction factor for the lanthanides and actinides was developed. After applying the correction factor, the percent difference between the net salt mass in the electrorefiner and the resulting modeled salt mass decreased from more than 4.0% to approximately 0.1%. As a result, there is no need to measure the salt density at 500 °C for inventory operations; the model for the salt density is found to be accurate.     

用于快堆非能动停堆系统的磁性连接对的设计优化与完整性综合评价

按照ASME规范要求,完成了用于快堆非能动停堆系统的磁性连接对的设计;对工况进行了分析,总结出了磁性连接对在正常运行工况下的载荷,并利用大型有限元分析软件ANSYS对连接对进行计算,得到正常运行工况下的应力值。按照ASME规范,对磁性连接对在正常运行工况下进行了应力强度分析和评定及疲劳评定。结果显示,磁性连接对在正常运行工况下的一次和二次应力强度及疲劳评定均满足ASME规范的要求。     

对我国核电标准体系总体设计的几点看法

根据我国压水堆核电厂标准体系建设规划的要求,经比较分析对兼容美国和法国相关标准来形成我国核岛机械系统和设备的设计和建造标准的途径提出了看法,提出了解决材料问题的建议,并呼吁编制我国的核电用户要求文件。     

ASME PCC-1—2019《压力边界螺栓法兰连接安装指南》的解析

螺栓法兰连接一直是压力容器使用与维护领域的重要内容,然而在实际生产过程之中,由于螺栓法兰连接的安装质量没有得到有效保证,导致了连接处发生泄漏。2000年ASME颁布了第一版《压力边界螺栓法兰连接安装指南》,并分别于2010年、2013年进行了修订,2019年又颁布了最新的ASME PCC-1—2019。ASME PCC-1—2019对2013版指南中存在的问题进行了修正,同时还基于工程实践经验,对指南进行了多处增删与更新,如删除了附录G《螺栓服务中承包商的使用》的内容,增加了一个最新的附录Q 《动力设备使用的注意事项》,并在附录O中引入了新的参考扭矩表。根据新版指南的修订内容,对ASME PCC-1—2019进行分析解读,为我国螺栓法兰连接的工程安装提供参考。     

对ASME B31.3工艺管道中关于柔性分析的理解

就管道柔性分析,如柔性分析和疲劳评定的关系,柔性分析中是否包括压力的影响等,以B31．3所规定的条文为依据提出看法,供讨论。     

Assessment of thermal aging embrittlement in a cast stainless steel valve and its effect on the structural integrity

This paper analyzes the thermal aging embrittlement occurred in a cast stainless steel valve, which is part of the reactor water clean-up (RWCU) system of a Spanish boiling water reactor (BWR) nuclear power plant. The aim is to estimate the current and future state of the material and the corresponding structural integrity of the valve. Given that there is no data available for the experimental characterization of the material, the evolution of the mechanical properties (fracture toughness, yield stress, flow stress and Ramberg-Osgood parameters) has been estimated using the ANL procedure.With the obtained estimations, the critical crack size has been calculated using the European procedure FITNET FFS and the ASME Code.This analysis considers not only the evolution of the mechanical properties up to now but also its future evolution in case there is a life extension of the plant until year 2029.     

Design Comparison of Coated Structures for High Heat Flux Components in Fusion Reactor

High heat flux components in fusion reactors are examined from a viewpoint of structural design. Maximum admissible steady heat flux, which can be absorbed and removed by coated structures, was determined by one-dimensional numerical analysis basing on ASME code Sec. HI. Comparison of the current candidate materials is made in order to make heat flux as high as possible. The following conclusions were obtained. (1) Be-Cu structure can be used in order to remove high heat flux beyond 10 MW/m², however, the strong chemical activity of Be gives rise to a problem. (2) SiC-HT-9 and SiC-V alloy structures are promising in case of high heat flux less than 2 MW/m². (3) From thermal stress analysis tungsten and graphite are excellent coating materials and are available for many structural materials. The study of thermal shock resistance and thermal fatigue of these materials is now a problem to be solved.