严重事故专用卸压阀排放能力需求

二代加百万千万级核电站严重事故下卸压过程中高温流体流经卸压阀,可能造成流道变形,甚至造成阀杆下落使得排放流道封闭,造成卸压失败。对严重事故专用卸压阀在卸压过程中可能经历的高温流体状态进行谱分析,获得了不同卸压能力下阀门经受的高温流体状态。开展了高温可能引起的阀门流道变形对卸压效果的影响分析。第二类阀门虽然存在阀门流道变形的可能,但能够获得较长严重事故处置时间,从优化严重事故对策的角度,严重事故专用卸压阀推荐采用第二类阀门排放能力450～600 t/h范围。     

Generation IV reactors and the ASTRID prototype: Lessons from the Fukushima accident

In France, the ASTRID prototype is a sodium-cooled fast neutron industrial demonstrator, fulfilling the criteria for Generation IV reactors. ASTRID will meet safety requirements as stringent as for 3rd generation reactors, and take into account lessons from the Fukushima accident. The objectives are to reinforce the robustness of the safety demonstration for all safety functions. ASTRID will feature an innovative core with a negative sodium void coefficient, take advantage of the large thermal inertia of SFRs for decay heat removal, and provide for a design either eliminating the sodium–water reaction, or guaranteeing no consequences for safety in case such reaction would take place.     

Causality-Network-Based Critical Hazard Identification for Railway Accident Prevention: Complex Network-Based Model Development and Comparison

This study investigates a critical hazard identification method for railway accident prevention. A new accident causation network is proposed to model the interaction between hazards and accidents. To realize consistency between the most likely and shortest causation paths in terms of hazards to accidents, a method for measuring the length between adjacent nodes is proposed, and the most-likely causation path problem is first transformed to the shortest causation path problem. To identify critical hazard factors that should be alleviated for accident prevention, a novel critical hazard identification model is proposed based on a controllability analysis of hazards. Five critical hazard identification methods are proposed to select critical hazard nodes in an accident causality network. A comparison of results shows that the combination of an integer programming-based critical hazard identification method and the proposed weighted direction accident causality network considering length has the best performance in terms of accident prevention.     

Two-lane traffic simulations with a blockage induced by an accident car

Based on the two-lane traffic model proposed by Chowdhury et al., a highway traffic model with a blockage induced by an accident car is proposed, in which both symmetric lane changing rules and asymmetric lane changing rules are adopted. The fundamental diagrams and spatial-temporal profiles are presented after the numerical simulation and the jam transition is studied. It is shown that the accident car not only causes a local jam behind the accident car, but also causes vehicles to cluster in the bypass lane. The asymmetric lane changing rules are more advantageous in reducing the local jam than the symmetric lane changing rules when the accident car is in the right lane, and the symmetric lane changing rules are superior when the accident car is in the left lane. Furthermore the curves of lane-changing frequency against the total density are given. It is found that the vehicles will change lane more frequently when traffic is inhomogeneous with different types of vehicle or with an accident car.     

HL-2A的中央逻辑控制PLC环网设计

PLC逻辑控制是HL-2A中央控制系统的重要组成部分,改造前的逻辑控制系统基本使用硬连接,维护耗时耗力。结合新一代实时工业以太网PROFINET为HL-2A逻辑控制系统的改造设计了环形冗余网络。采用8台西门子交换机SCALANCE X200通过光纤依次连接成环,交换机的电口连接S7-400和上位机,与等离子体放电相关的重要信号仍走硬连接,其他所有信号都走网络传送。中控系统作为管理站对其他7个子系统进行集中化管理,中控可以轻松快速地获取每个子系统的状态,在等离子体放电错误时能很快的预测事故地点和故障分析。根据放电实验结果表明,光纤环网非常适用于设备分散的慢控制系统,整个控制系统逻辑关系清楚,后期扩展和改造也非常方便。改造后的逻辑控制系统能满足HL-2A和HL-2M两套装置的慢控制,维护简便,事故定位快准,提高了放电效率。     

Analyzing the causation of a railway accident based on a complex network

In this paper, a new model is constructed for the causation analysis of railway accident based on the complex network theory. In the model, the nodes are defined as various manifest or latent accident causal factors. By employing the complex network theory, especially its statistical indicators, the railway accident as well as its key causations can be analyzed from the overall perspective. As a case, the ＂7.23＂ China-Yongwen railway accident is illustrated based on this model. The results show that the inspection of signals and the checking of line conditions before trains run played an important role in this railway accident. In conclusion, the constructed model gives a theoretical clue for railway accident prediction and, hence, greatly reduces the occurrence of railway accidents.     

Continuously improving safety of nuclear installations: An approach to be reinforced after the Fukushima accident

After the Three Mile Island accident in 1979 and the Chernobyl accident in 1986, the Fukushima accident shows that the probability of a core meltdown accident in an LWR (Light Water Reactor) has been largely underestimated. The consequences of such an accident are unacceptable: except in the case of TMI2 (Three Mile Island 2) large areas around the damaged plants are contaminated for decades and populations have to be relocated for long periods. This article presents the French approach which consists in improving continuously the safety of the Nuclear Power Plants (NPP) on the basis of lessons learned from operating experience and from the progress in R&D (Research and Development). It details the key role played by IRSN (Institut de radioprotection et de sûreté nucléaire), the French TSO (Technical and scientific Safety Organization), and shows how the Fukushima accident contributes to this approach in improving NPP robustness. It concludes on the necessity to keep on networking TSOs, to share knowledge as well as R&D resources, with the ultimate goal of enhancing and harmonizing nuclear safety worldwide.     

考虑意外事件对交通流影响的元胞自动机交通流模型

在NaSh模型的基础上,考虑交通事故和养护路段等意外事件对高速公路交通流的影响,建立了有意外事件影响的在车道管制下的高速公路交通流元胞自动机模型,并进行数值模拟. 研究发现:意外事件对高速公路交通流有明显影响,并且意外事件对交通流的影响在某一密度值范围内尤其明显,且意外事件堵塞点在第一车道比在第二车道对交通流的影响小;同时,在该密度值范围内,意外事件堵塞时间和堵塞路段长度越长,对交通流的影响就越大. 关键词： 元胞自动机 交通流 意外事件     

Simulation test research on incendive ESD in tanker cargo

This paper, considering an explosive accident of a tanker last year in China, analyzes and evaluates the safety property of electrostatics on tanker cargo during the drainage of ballast water. Based on the simulation test investigation and theoretical analysis about this accident, the current paper indicates that the tanker exploded probably because the steam pipe fixed in the cargo leaked. A lot of steam sprayed and a very high static field was formed in the cargo. An insulated conductor (a copper rod or flashlight) happened to fall into the tank. Some ESD spark caused the explosion. This paper proposes some suggestions to avoid such an accident.     

Simulation of COPO II Lo experiments on natural convection of heat generating liquid at high Rayleigh numbers

The methodology is described and the results are presented concerning numerical modeling of COPO II Lo experiments on heat transfer in liquid with internal heat generation at very high internal Rayleigh numbers typical for natural convection in a core melt that can appear during progress of severe accident at a nuclear power plant (NPP). The work is keeping in the course of development of CFD-based tool for quantitative analysis of heat transfer in a stratified molten pool of different configurations possible in severe accident scenarios with melt retention in the reactor vessel or in the VVER core catcher. Such CFD methodology would be used for testing of simplified correlation models for simulation of the core melt interaction with NPP structures in system code SOCRAT. During verification the available experimental data on the core melt thermohydraulics were analyzed, and it was concluded that they are insufficient to measures of CFD quality. The data uncertainties, along with the complexities of convective flow, uncertainties of the reactor core melt conditions, limitations of experimental possibilities and of turbulence modeling, actually constrain the multivariate CFD simulations of natural convection at very high Rayleigh numbers. RANS turbulence models only can be efficiently applied here, and they are to be checked for such purposes. In a series of numerical modeling of COPO II Lo experiments and some others, availability of a k-? realizable model with included buoyancy effects was estimated, and the optimal set of CFD options was formed for minimizing numerical artifacts. It was demonstrated that in the investigated range of Rayleigh numbers the k-? model works qualitatively correctly, but is inclined to systematical deformation of the melt boundary heat transfer distribution. This allows one to use this model for qualitative multivariate CFD estimations but requires improvement of the model or finding of its efficient and more exact equivalent.     

交通事故中汽车速度分析物理模型的研究

对交通事故的汽车碰撞进行简化分析,运用经典物理定律研究了汽车碰撞,较为简洁的分析了汽车碰撞过程中速度复杂的变化,希望在科学处理交通事故中提供一种简单方法。     

CN HCCB TBS 的LOFA 与真空室内LOCA 初步分析

基于CN HCCB TBS 的最新设计,用RELAP 5 软件对失流事故(LOFA)和真空室内失冷事故(In-vessel LOCA)这两种假设基本事故进行了分析。结果表明,CN HCCB TBS 在这两种事故工况下的安全性是有保证的,并且热工水力学瞬态分析能给出有关发生事故时TBM 安全性相关性能的信息,从而提出了所需要的各种安全保护系统及其动作的时间。     

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基于CN HCCB TBS的最新设计,用RELAP 5软件对失流事故(LOFA)和真空室内失冷事故(In-vessel LOCA)这两种假设基本事故进行了分析。结果表明,CN HCCB TBS在这两种事故工况下的安全性是有保证的,并且热工水力学瞬态分析能给出有关发生事故时 TBM 安全性相关性能的信息,从而提出了所需要的各种安全保护系统及其动作的时间。     

事故地点对交通波的影响研究

利用唐等人提出的考虑事故概率的交通流模型［Tang T Q, Huang H J, Xu G 2008 Physica A 387 6845］研究事故发生地点对冲击波和稀疏波的影响,其数值计算结果表明,该模型可以如实地刻画事故对这两种交通波的影响,但这种影响与事故发生地点密切相关. 关键词： 交通事故 冲击波 稀疏波     

基于元胞传输模型的可变信息标志选址问题研究

随着智能交通技术的发展，可变信息标志(VMS)被广泛应用于动态交通管理中.元胞传输模型(CTM)可以较好地模拟交通流激波、排队形成与消散等交通流动力学特性.应用CTM对VMS选址问题进行了研究.数值模拟结果表明，合适的VMS位置可以减少系统内所有车辆的行驶时间.还分析了路径选择概率变化与VMS位置之间的关系.在一定范围内，交通事故越严重，VMS应设置在距离事故地点越远的地方. 关键词： 可变信息标志 选址问题 元胞传输模型 数值模拟     

The relations of “go and stop” wave to car accidents in a cellular automaton with velocity-dependent randomization

In this paper we numerically study the probability P_ac of the occurrence of traffic accidents in the Nagel-Schreckenberg (NS) model with velocity-dependent randomization (VDR). Numerical results show that there is a critical density over which car accidents occur, but below which no car accidents happen. Different from the accident probability in the NS model, the accident probability in the VDR model monotonously decreases with increase of car density above the critical density. The value of the accident probability is only determined by the stochastic noise and the number of cars on road. In the stochastic VDR model with the speed limit v_max=1, no critical density exists and car accidents happen in the whole density region. The braking probabilities of standing cars and moving cars have different influences on the accident probability. A mean-field theory reveals that the accident probability is proportional to the mean density of “go and stop” wave per time step. Theoretical analyses give excellent agreement with numerical results in the VDR model.     

动态故障树在主蒸汽管道破裂事故风险评价中的初步应用研究

冗余设计使核电厂系统广泛存在复杂时序失效行为,而基于静态故障树(Static fault tree, SFT)的事故风险评价无法对时序失效行为进行准确模拟。为解决这一问题,本工作提出一种基于事件树+动态故障树(Dynamic Fault Tree, DFT)的事故风险分析框架,并以典型三代压水堆主蒸汽管道破裂事故为例,开展动态事故风险案例分析。首先,建立主蒸汽管道破裂事故的事件树模型以及相关系统的DFT模型;其次,将系统故障树分为DFT模块和SFT模块,并将DFT树模块替换为超级事件参与后续计算;最后,采用割集法计算案例结果,并在相同条件下与传统SFT方法进行对比。案例分析结果表明：(1)相较于SFT方法,所提方法更为贴近系统的真实失效场景;(2)针对文中案例所提方法可以降低相关系统失效概率与部分事故序列的发生频率、有助于释放保守风险。     

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ITER聚变装置在运行过程中会产生大量的灰尘,当发生事故冷却水进入时,与热的灰尘发生反应产生氢气。氢气聚集后可能会燃烧甚至爆炸,对装置产生破坏。运用CFD的方法对“Wet Bypass”事故后反应产生的氢气风险进行了分析评价,得出在事故的初始阶段氢气达到了燃爆的风险,不同流量的冷却水泄漏进入真空室内会带来不同的氢气风险强度,在冷却水进入量十分大的情况下会惰化灰尘产生的氢气风险。并对注入二氧化碳惰化真空室气体空间的措施进行了分析,在事故发生的初期以较大速率充入二氧化碳能够降低氢气带来的风险。     

Dose assessment in the criticality accident at Tokai-mura

The present paper reviews a dose assessment carried out after the criticality accident that occurred on September 30, 1999 at JCO in Tokai-mura, Japan. In the accident, almost all doses were caused by external exposure to neutrons and γ-rays emitted upon the fission of uranium. By a joint effort of Japanese experts in radiation dosimetry, a dose assessment was performed for neighboring residents, JCO employees including 3 workers who were at the accident spot, and emergency response personnel. The dose assessment was carried out using records of dosimeters, radiation monitoring data in and around the site, analysis of biological specimens, and computer simulation techniques. It was concluded from the results of the dose assessment that deterministic effects are not expected, except for the 3 heavily exposed workers, and that the probability of stochastic effects is very small and will be undetectable.