基于火焰加速和燃爆转变准则的氢气点火安全性研究

采用点火器对可燃混合气体进行预先点火是严重事故下的1种可供选择的氢气缓解措施。基于σ准则和λ准则可以评估氢气燃烧时发生火焰加速(FA)和爆燃向爆炸的转变(DDT)的可能性。本文分析密闭房间中氢气早期和晚期点火的过程。分析结果表明，点火器在空间的合理布置和初次点火时间的控制，可有效移除事故前期的氢气。本方法能用于确定核电站干式安全壳内氢气点火器的数量、位置和点火时间。     

Visualizing an ignition process of hydrogen jets containing sodium mist by high-speed imaging

In severe accident scenarios for sodium-cooled fast reactors, it is desirable to gradually consume hydrogen generated by various ex-vessel phenomena without posting a challenge to containment integrity. An effective means is combustion of hydrogen jets containing sodium vapor and mist, but previous studies have been limited to determining ignition thresholds experimentally. The aim of this study was to visualize the ignition process in detail to investigate the ignition mechanism of hydrogen–sodium mixed jets. The ignition experiments of the hydrogen jet containing sodium mist were carried out under a condition of little turbulence. The ignition process was measured with an optical measurement system comprised of a high-speed camera and an image intensifier, and a spatial distribution of luminance was analyzed by image processing. Detail observation revealed that sodium mist particles burned as scattering sparks inside the jet and that hydrogen ignited around the mist particles. Additionally, the experimental results and a simple heat balance calculation indicated that the combustion heat of sodium mist particles could ignite the hydrogen as the heterogeneous ignition source in the fuel temperature range where the mist particle formation was promoted.     

AP1000小破口叠加重力注射失效严重事故分析

应用新版MELCOR程序,建立了AP1000一二回路、非能动安全系统及安全壳隔室的热工水力模型,并以热段小破口叠加重力注射系统失效事故为例,对该严重事故进程在压力容器内阶段进行模拟计算,对缓解措施的功能进行了分析和评价。结果表明：自动卸压系统（ADS1～4）的成功实施,可使来自堆芯补水箱和安注箱的冷却水快速有效地注入堆芯,在冷却水完全耗尽前,堆芯始终处于淹没的状态。ADS4爆破阀开启后,使回路压力快速与安全壳压力平衡;非能动安全壳冷却系统对抵御严重事故下由于衰变热和非冷凝气体带来的缓慢升温升压是行之有效的措施;点火器在氢气浓度较低时点火,缓解了安全壳大空间发生全局燃爆而引发安全壳超压失效的风险,但连续点火燃烧会引起局部隔室温升远超出设计温度而危及后备缓解设施的存活。     

Air-hydrogen deflagration tests at the University of Pisa

In severe accidents, large amounts of hydrogen may be released in the safety containment of a nuclear plant and the gas mixture may become explosive. The University of Pisa and ENEA have undertaken an experimental program to study the physics of flame propagation in a containment model under accident conditions. Up to now 41 deflagration tests have been performed at the HYDRO-SC facility at ambient pressure and temperature. Concentrations, water spray conditions, ignition source and gas turbulence levels were varied. The vessel volume was 0.5 m³, the ignition sources were an electrical spark discharge and an electrically heated surface (glow-plug), the hydrogen molar fractions were in the range 4–16%, the turbulence was generated by fan or spray and two different spray nozzles were utilized. The experimental data indicate that the peak pressures nearly fit the adiabatic isochoric values at the highest hydrogen concentrations and gas turbulences. Weak pressure waves were observed for H₂ molar fractions greater than 10%. A careful examination of the pressure and temperature transients gave information on the flame path and on the heat transfer process during and after combustion. Scale effects on the peak pressures were not observed by comparison of the HYDRO-SC results with data obtained in other laboratories. The glow plug igniter has proved to be a reliable tool for use in deliberate ignition schemes for hydrogen control in nuclear plants.     

Hydrogen and steam distribution following a small-break LOCA in large dry containment

The hydrogen deflagration is one of the major risk contributors to threaten the integrity of the containment in a nuclear power plant, and hydrogen control in the case of severe accidents is required by nuclear regulations. Based on the large dry containment model developed with the integral severe-accident analysis tool, a small-break loss-of-coolant-accident （LOCA） without HPI, LPI, AFW and containment sprays, leading to the core degradation and large hydrogen generation, is calculated. Hydrogen and steam distribution in containment compartments is investigated. The analysis results show that significant hydrogen deflagration risk exits in the reactor coolant pump （RCP） compartment and the cavity during the early period, if no actions are taken to mitigate the effects of hydrogen accumulation.     

氢气催化复合器对核电厂严重事故的缓解效果

在严重事故条件下,安全壳内的氢气燃烧或爆炸威胁安全壳完整性,必须采取措施减小或消除安全壳的氢气风险。针对600MWe级核电厂的大型干式安全壳,以小破口失水诱发的严重事故序列为基准事故,计算分析了氢气催化复合器（PAR）消除安全壳内氢气的效果,及复合效应对安全壳压力温度的影响。研究表明：氢气催化复合器能够持续稳定地消除安全壳内氢气,但对于极其快速的氢气释放,它的消氢能力受到一定限制。     

先进压水堆核电站氢气风险分析

核电厂在严重事故期间会产生大量氢气并释放到安全壳内,威胁安全壳的完整性。应用氢气风险分析程序GASFLOW对先进压水堆核电站在大破口失水事故叠加应急堆芯冷却系统失效导致的严重事故期间的氢气行为及风险进行分析。结果表明,当气体释放源位于蒸汽发生器隔间时,氢气流动的主要路径为"蒸汽发生器隔间—穹顶空间—操作平台以下隔间";破口隔间的氢气体积浓度分布与源项氢气体积浓度及射流形态有关,非破口区域的氢气体积浓度呈层状分布,在扩散作用下,层状分布向下推移;蒸汽发生器隔间存在着火焰加速(FA)的可能性,但基本可排除燃爆转变(DDT)的可能性,穹顶区域基本可排除FA和DDT的可能性。     

A study on evaluating a passive autocatalytic recombiner PAR-system in the PWR large-dry containment

A systematic step-by-step framework for analyzing hydrogen behavior and implementing passive autocatalytic recombiners (PARs) to mitigate hydrogen deflagration or detonation risk in severe accidents (SAs) is presented. The procedure can be subdivided into five main steps: (1) modeling the containment based on the plant design characteristics, (2) selecting the typical severe accident sequences, (3) calculating the hydrogen generation including in- and ex-vessel period, (4) modeling the gas distribution in containment atmosphere and estimating the hydrogen combustion modes and (5) evaluating the efficiency of the PAR-system to mitigate the hydrogen risk with and without catalytic recombiners, according to the safety criterion. For the Chinese 600MWe pressurized water reactor (PWR) with a large-dry containment, large break loss-of-coolant accident (LB-LOCA) is screened out as the reference severe accident sequence, considering the nature of hydrogen generation and the probabilistic safety assessment (PSA) result on accident sequences. The results show that a certain number of recombiners could remove effectively hydrogen and oxygen, to protect the containment integrity against hydrogen deflagration or detonation.     

严重事故下安全壳卸压箱隔间氢气浓度场模拟

根据MELCOR程序对全厂断电诱发的严重事故下安全壳内各隔间的氢气浓度分布的计算结果,参考美国联邦法规关于氢气控制和风险分析的标准,分析安全壳内氢气的燃烧风险。结果表明：安全壳内平均氢气浓度不会导致整体性氢气燃烧,但存在局部燃烧的风险。通过CFD程序对氢气浓度较高的卸压箱隔间进行氢气释放和空间气体流动过程的模拟,得到更细致的卸压箱隔间内氢气浓度场分布,给出氢气聚集区域的准确位置,为采取严重事故缓解措施,设计氢复合器布置方案提供了参考依据。     

Flow transport and mixing induced by horizontal jets impinging on a vertical wall of the multi-compartment PANDA facility

In the frame of the OECD/NEA SETH project an experimental campaign has been carried out in the PANDA facility to investigate gas transport and mixing induced by a plume or a jet in the large-scale multi-compartment PANDA facility. The paper summarizes the results of the horizontal jet test series consisting of eight tests. Horizontal jets impinging on a vertical wall of one of the cylindrical PANDA containment vessels have been generated by changing various parameters, such as: type of injected fluid (steam or a mixture of steam and helium), fluid injection velocity, elevation (with respect to the containment vessel) of the injection exit, initial fluid composition in the vessels, and location of the vent line. The initial jet Froude number has been varied between 17 and 36 and in one of the test condensation occurred. The paper shows the effect of these parameters variation on the test evolution with respect to jet impingement location in the vertical curved wall and variation of impingement location as a function of buoyancy variation. Fluid mixing and stratification, characteristics of gas transport between the compartment and the effect of condensation on the overall phenomena evolution are analyzed in the paper.     

Three-dimensional behaviors of the hydrogen and steam in the APR1400 containment during a hypothetical loss of feed water accident

During a hypothetical severe accident in a nuclear power plant (NPP), hydrogen is generated by an active reaction of the fuel-cladding and the steam in the reactor pressure vessel and released with the steam into the containment. In order to mitigate hydrogen hazards which could possibly occur in the NPP containment, a hydrogen mitigation system (HMS) is usually adopted. The design of the next generation NPP (APR1400) developed in Korea specifies that 26 passive autocatalytic recombiners and 10 igniters should be installed in the containment for a hydrogen mitigation. In this study, an analysis of the hydrogen and steam behavior during a total loss of feed water (LOFW) accident in the APR1400 containment has been conducted by using the computational fluid dynamics (CFD) code GASFLOW. During the accident, a huge amount of hot water, steam, and hydrogen is released into the in-containment refueling water storage tank (IRWST). The current design of the APR1400 includes flap-type openings at the IRWST vents which operate depending on the pressure difference between the inside and outside of the IRWST. It was found from this study that the flaps strongly affect the flow structure of the steam and hydrogen in the containment. The possibilities of a flame acceleration and a transition from deflagration to detonation (DDT) were evaluated by using the Sigma–Lambda criteria. Numerical results indicate that the DDT possibility was heavily reduced in the IRWST compartment by the effects of the flaps during the LOFW accident.     

Application study on plasma ignition in aeroengine strut-cavity-injector integrated afterburner

To increase the thrust-weight ratio in next-generation military aeroengines,a new integrated afterburner was designed in this study.The integrated structure of a combined strut-cavity-injector was applied to the afterburner.To improve ignition characteristics in the afterbumer,a new method using a plasma jet igniter was developed and optimized for application in the integrated afterburner.The effects of traditional spark igniters and plasma jet igniters on ignition processes and ignition characteristics of afterburners were studied and compared with the proposed design.The experimental results show that the strut-cavity-injector combination can achieve stable combustion,and plasma ignition can improve ignition characteristics.Compared with conventional spark ignition,plasma ignition reduced the ignition delay time by 67 ms.Additionally,the ignition delay time was reduced by increasing the inlet velocity and reducing the excess air coefficient.This investigation provides an effective and feasible method to apply plasma ignition in aeroengine afterburners and has potential engineering applications.     

严重事故下氢气风险及氢气控制系统的初步分析

采用一体化严重事故分析工具,对600MWe压水堆核电厂严重事故下氢气风险及拟定的氢气控制系统进行分析。结果表明：相对于小破口失水始发事故和全厂断电始发事故工况,大破口失水始发严重事故堆芯快速熔化,在考虑100%锆 水反应产氢量的条件下,大破口失水始发事故氢气风险较大,有可能发生氢气快速燃烧;在氢气控制系统作用下,发生大破口失水始发严重事故时,安全壳内平均氢气浓度和隔间内氢气浓度低于10%,未达到氢气快速燃烧和爆炸的条件,满足美国联邦法规10CFR中关于氢气控制和风险分析的准则,认为该氢气控制系统是可行、有效的。     

H_2/O_2爆燃波在冷源真空筒内的传播

若反应堆冷中子源真空筒热交换器中H2冷却剂泄漏与空气混合时,H2与O2发生爆炸,其冲击波将对真空筒完整性构成威胁。采用全尺寸模拟件进行实验,研究爆燃波对真空筒的冲击程度。比较在不同当量比和初压H2/O2混合物,在模拟件内点火引发爆燃,采用压力、火焰测量和数据采集系统,测量各测点的火焰及压力时间曲线。结果表明,低初压和化学当量比两种工况产生的冲击波和火焰均可通过真空筒点火端经狭缝进入到另一端,并形成强爆燃。对富油(即H2过剩)工况,管道只产生低速燃烧,无冲击波特征。     

非能动安全壳局部分层及分区计算研究

搭建小型非能动钢制安全壳台架,以蒸汽为工质,通过实验研究破口事故下非能动安全壳内的环流与热分层现象。结果表明：不同的喷射流量下,安全壳内均存在分层现象;分层属于局部分层而非大空间整体分层。对当前国内外常用的安全壳计算程序进行对比分析,并结合实验研究结果,提出一种根据壳内传热和流动的特点进行分类分区,然后再各自建立模型进行计算的新方法。     

Effect of shock wave formation on propellant ignition in capillary discharge

In order to study the effect of shock wave formation on propellant ignition in capillary discharge, the shock wave formation process was analyzed using experimental and theoretical methods; the plasma jet temperature was measured, and closed bomb and 30 mm gun experiments were carried out. The results show that the first shock wave has a smaller value and larger range of influence, while the second shock wave has a larger value and smaller range of influence. A plasma jet can generate a shock wave at the nozzle according to the calculated plasma pressure and velocity, which is well confirmed by experiments and calculations. The plasma jet temperature is high during the formation of a shock wave and then decreases sharply. Plasma ignition can increase the burning rate of a propellant by about 30% by increasing the burning surface area of the propellant. Compared to conventional ignition, the average maximum chamber pressure and average muzzle velocity of plasma ignition are increased by 9.1 MPa and 29.3 m·s−1(∼3%), respectively, in a 30 mm gun. Plasma ignition has strong ignition ability and short ignition delay time due to the generation of a shock wave. By increasing the burning rate of the propellant, the muzzle velocity can be greatly improved when the maximum chamber pressure increases a little. The characteristics of the shock wave can be applied in the application of the capillary discharge plasma. For example, it can be applied in fusion, launching and combustion.     

The position of hybrid reactors in power-generation systems

Conclusion The range of application of hybrid reactors in power generation depends on laws of plasma physics with reactor parameters which have not yet been studied experimentally. If the plasma containment is close to the empirical law, or better, then the production of plutonium in the blanket of a fusion reactor with ignition justifies the capital expenditure on the construction of a power station of up to $700/kW.If ignition of the reaction is technically or economically unprofitable, closed reactors with injection might serve for the commercial production of electric power and might be pure, as well as in the form of hybrids, and open reactors only in the form of hybrids. At the present-day level of knowledge, the least number of unsolved problems for the design of hybrid reactors has remained for open magnetic traps (problem of containment). Stellerators occupy the second place (the problem of contaminants is added) and in third place are the Tokamaks (the problem of steady-state maintenance of the current in the plasma still must be solved).We note that containment in one-hundred Bohm periods, assumed to be the worst for Tokamaks and Stellerators, has not yet been achieved in a single experiment. Therefore, all forecasts on the possibility of better containment in reactor cycles up to now have no experimental foundation whatsoever. The next five year period must bear some clarification of this most important question.Translated from Atomnaya Énergiya, Vol. 39, No. 6, pp. 379–386, December, 1975.     

A Steam-Plasma Igniter for Aluminum Powder Combustion

High-temperature ignition is essential for the ignition and combustion of energetic metal fuels,including aluminum and magnesium particles which are protected by their highmelting-temperature oxides.A plasma torch characterized by an ultrahigh-temperature plasma plume fulfills such high-temperature ignition conditions.A new steam plasma igniter is designed and successfully validated by aluminum power ignition and combustion tests.The steam plasma rapidly stabilizes in both plasma and steam jet modes.Parametric investigation of the steam plasma jet is conducted in terms of arc strength.A high-speed camera and an oscilloscope method visualize the discharge characteristics,and optical emission spectroscopy measures the thermochemical properties of the plasma jet.The diatomic molecule OH fitting method,the Boltzmann plot method,and short exposure capturing with an intensified charge coupled device record the axial distributions of the rotational gas temperature,excitation temperature,and OH radical distribution,respectively.The excitation temperature at the nozzle tip is near 5500 K,and the gas temperature is 5400 K.     

Reliability analysis of nuclear containment without metallic liners against jet aircraft crash

The present study presents a methodology for detailed reliability analysis of nuclear containment without metallic liners against aircraft crash. For this purpose, a nonlinear limit state function has been derived using violation of tolerable crack width as failure criterion. This criterion has been considered as failure criterion because radioactive radiations may come out if size of crack becomes more than the tolerable crack width. The derived limit state uses the response of containment that has been obtained from a detailed dynamic analysis of nuclear containment under an impact of a large size Boeing jet aircraft. Using this response in conjunction with limit state function, the reliabilities and probabilities of failures are obtained at a number of vulnerable locations employing an efficient first-order reliability method (FORM). These values of reliability and probability of failure at various vulnerable locations are then used for the estimation of conditional and annual reliabilities of nuclear containment as a function of its location from the airport. To study the influence of the various random variables on containment reliability the sensitivity analysis has been performed. Some parametric studies have also been included to obtain the results of field and academic interest.     

实验模拟非能动安全壳冷却系统中因破口喷射诱发的传热增长(英文)

介绍在自然对流中由强迫喷射所造成的传热增长。实验研究了在具有垂直冷却面的大型矩形腔体中因强迫射流造成的混合对流传热。在模拟实际非能动安全壳冷却系统及接近实际安全壳分隔区域尺寸的条件下,测量了控制强迫射流传热的关键参数,研究了包括喷射直径、喷射方向、内部构件和腔体比例在内的几何因子的影响。本实验包括了多种射流模式,有助于揭示新一代固有安全型反应堆在事故条件下内部的混合与分层现象。通过控制方程的相似律分析,可预言混合对流传热由阿基米德数和几何因子控制。利用混合对流传热的组合律及飘浮型和碰撞型射流的数学模型,推导出了传热增长关系式,并经过了实验数据测试。通过对实验结果的分析阐明了喷射直径、喷射方向、内部构件和腔体比例对传热增长的影响。