Evaluation of the containment vessel failure time from operator’s notifications during a severe accident

This paper aims at clarifying the potential and the limit of the method to surmise the timing of the containment vessel (CV) failure utilizing the Emergency Action Levels (EALs) issued as a nuclear operator’s notification in an early phase of the severe accident (SA). We analyzed the timings of the EALs issued in all kinds of the SA sequences of several PWR plant models by using the SA analysis code, MAAP. We found high correlations between the timing of SE41 (EAL issued at CV pressure of 0.5 design pressure) and the timing of the CV failure in the typical scenarios, e.g. over-pressure failures. We could therefore establish an evaluating method to estimate the time for a CV failure. This method has the potential to support the decision-making in nuclear emergency preparedness.     

基于AHP的旗袍胸部压力舒适性研究

为改善旗袍胸部牵制感与压迫感,提高旗袍的胸部压力舒适性,对同一结构规格旗袍的门襟、袖型及穿脱方式进行设计组合,利用正交试验制作旗袍样衣,测试出受试者在规定动作下的主客观压力值,并利用AHP法对主客观数据进行综合分析,得出对旗袍压力舒适性影响最大的设计因素及动作。结果表明,双侧门襟、无袖及前门襟穿脱方式的设计因素可以在一定程度上缓解旗袍胸部牵制感和压迫感,提高穿着舒适性;其中袖型因素服装压力值波动最大,对旗袍胸部压力舒适性影响程度更为显著;而规定动作中双手背后这一动作所占权重最高,对旗袍胸部压力舒适性的影响最大。     

Measurement of heat transfer coefficients for steam condensation on a vertical 21.5-mm-O.D. tube in the presence of air

ABSTRACT

Governing the rate of heat transport by condenser tubes in the passive containment cooling system (PCCS), the steam condensation over a vertical cylinder in the presence of air was investigated experimentally. The main objective of this study was to explore if the condensation heat transfer coefficient relies on the tube dimension, which has been a variable missed in most condensation models or has been embraced without experimental demonstration under phase change environments. The mean heat transfer coefficient was measured in the condensation test facility named JERICHO (JNU Experimental Rig for Investigation of Condensation Heat transfer On tube). The outer diameter of the condenser tube used in this study was set to 21.5 mm. The measured heat transfer coefficients were compared to those obtained from the 40-mm-O.D. tube, and a multiplier to correct the variation of the heat transfer coefficient with the tube diameter was proposed for its application to Lee correlation. The proposed correlation was further validated against another set of experimental data obtained from a separate test facility housing the 31.8-mm-O.D. tube.     

非径向管板焊接接头的超声检测

对AP1000压水堆核电站安全壳贯穿件的非径向管板焊接接头结构特点进行了介绍,并分析其超声检测工艺的重点和难点。通过建立统一的缺陷定位坐标系并结合被检构件的几何特点进行综合分析,推导得出了h值(缺陷回波最高点距套管外壁的距离)的计算方法。为超声检测对这类焊接接头缺陷的准确识别和定位提供了行之有效的方法,为解决这类焊接接头的超声检测技术受限区提供了行之有效的措施。     

Structural integrity assessment of nuclear containment through fracture characterization

The paper deals with the study of structural response of partially cracked nuclear containment model structure in over pressurized condition with the simulated experiments conducted under severe accidents analysis program for Indian nuclear containment structures. In this research, the fracture characterization of concrete containment structure is also investigated through the over pressure experiments on the BARC Containment (BARCOM) test model structure, which represents 1:4 scale of the prototype 540 MWe Tarapur pre‐stressed nuclear containment structure. In addition to the surface‐type electrical resistance, strain gauges conventionally and commonly deployed for containment proof‐test and ultimate load capacity evaluation of containment models, embedded vibratory wire strain gauges (VWSGs), the digital image correlation (DIC) technique, and soap bubble tests are employed in this study. For fracture characterization, an optical crack profile (OCP) technique is developed through DIC full‐field experiment conducted at the identified critical locations with conventional strain gauges to evaluate the fracture energy and the characteristics of the fracture process zone of concrete containment model structure subjected to the over‐pressure condition for its performance assessment in the case of the beyond design basis accidents. The combination of conventional sensors and full‐field DIC deployed for the first time on the largest scale containment model along with the associated analysis is shown to be effective in fracture characterization and improved structural integrity assessment of the containment model.     

Observer‐based adaptive optimal output containment control problem of linear heterogeneous Multiagent systems with relative output measurements

This paper develops a relative output‐feedback–based solution to the containment control of linear heterogeneous multiagent systems. A distributed optimal control protocol is presented for the followers to not only assure that their outputs fall into the convex hull of the leaders' output but also optimizes their transient performance. The proposed optimal solution is composed of a feedback part, depending of the followers' state, and a feed‐forward part, depending on the convex hull of the leaders' state. To comply with most real‐world applications, the feedback and feed‐forward states are assumed to be unavailable and are estimated using two distributed observers. That is, a distributed observer is designed to measure each agent's states using only its relative output measurements and the information that it receives by its neighbors. Another adaptive distributed observer is designed, which uses exchange of information between followers over a communication network to estimate the convex hull of the leaders' state. The proposed observer relaxes the restrictive requirement of having access to the complete knowledge of the leaders' dynamics by all the followers. An off‐policy reinforcement learning algorithm on an actor‐critic structure is next developed to solve the optimal containment control problem online, using relative output measurements and without requiring the leaders' dynamics. Finally, the theoretical results are verified by numerical simulations.     

疏水性安全壳壁面的硅表面微孔结构制备

为构建疏水性安全壳内壁面涂层以提高事故中的传热能力,以Si作为功能涂层材料,在其表面上制备了不同圆孔间距及圆孔深度的微孔阵列样品以研究微米结构对表面疏水特性的影响,并对其疏水机理进行分析。结果表明,所制备的微孔样品润湿特性均符合Cassie-Baxter模型,在本征接触角为69.5°的Si表面通过微孔结构调控可显著提高疏水特性,获得了具有140°接触角的优异疏水特性样品而未进行表面化学修饰。研究结果为设计安全壳涂层材料及其表面微结构提供了技术方案,为强化核电站非能动安全壳冷却系统传热性能提供了解决思路。     

地下水封石油洞库施工期安全风险评估研究

地下水封石油洞库建设具有投资大、无成熟设计施工规范、不确定因素多等特点,建设过程中存在着一定安全风险,开展地下水封石油洞库施工期安全风险评估研究具有重要意义。针对地下水封石油洞库施工期安全风险,从洞库稳定性与水封性两个方面,开展了洞库施工期安全风险评估研究,结合中国首座大型地下水封石油洞库工程对研究结论进行了验证。研究中,开展了地下水封石油洞库风险因子识别,进行了风险因子重要性和引发功能失效概率调查;采用模糊数学方法获得了风险因子模糊权重集和模糊评价集,得到了风险因子影响程度排序;总结了某地下水封石油洞库建设中典型稳定性和水封性风险事故,分析了事故发生原因,并与上文所得风险因子影响程度进行了对比验证。研究结果不但为提高地下水封石油洞库风险管理水平提供支撑,而且还可丰富地下工程安全风险评估研究内容。     

Hydrodynamical particle containment in a rotor‐stator spinning disk device

A novel type of rotor‐stator spinning disk device is proposed which allows for the entrapment of solid particles solely by hydrodynamic means. In this new configuration, the solid rotating disk is replaced with two conjoined rotors with a variable gap spacing. Liquid is fed through the top stator and can flow out again through the rotor‐rotor interior and the hollow rotation axis. Moreover, the volume between the two rotors is optionally filled with a highly porous reticulated carbon foam. It was found that particle containment was strongly improved by the presence of this reticulated foam as it hinders the buildup of centripetal boundary layer flow near the disks in the interior of the rotor‐rotor assembly. These centripetal boundary layers drag along particles resulting in a loss of containment. Experiments utilizing glass beads showed that particles with a diameter down to 17.8 µm can be completely entrapped when a carbon foam is placed between the two conjoined disks at rotor speeds up to the maximum investigated value of 178 rad s^?1. Additionally, the rotor‐rotor gap did not have an effect on the particle entrapment level when the reticulated carbon foam was omitted and can be ascribed to the build‐up of boundary layers, which is independent of rotor‐rotor distance. © 2015 American Institute of Chemical Engineers AIChE J, 61: 3656–3665, 2015     

应用DAKOTA程序耦合WGOTHIC程序进行安全壳压力响应敏感性分析

安全壳压力响应分析是验证非能动安全壳冷却系统(PCS)设计的重要内容,需考虑PCS的传热传质等各种现象的影响。本文应用DAKOTA程序耦合WGOTHIC程序对大型先进压水堆非能动安全壳压力响应进行敏感性分析,通过偏相关系数,定量评价了重要现象识别和排序表(PIRT)中各种现象对安全壳压力的影响程度。研究结果表明:质能释放现象、安全壳内初始环境条件、冷凝/蒸发现象显著影响安全壳压力。该研究结果为安全壳设计、安全分析和安全审评提供技术支持。