Numerical studies of impact on reinforced concrete beam of hard missile

The safety design of concrete containment structures in nuclear power stations has thus far covered only accidents due to internal pressure, temperature loading and earthquake loading. Recently, designers and researchers have become interested in the important effects of the impact load of a projectile on nuclear power stations. This paper develops an FEM model for analyzing the collision of a hard missile against reinforced concrete structures and compares the results with impact tests conducted at our institute.     

Missile impact on a reinforced concrete structure

In this analysis an attempt was made to study the behaviour of a reinforced concrete structure under missile impact loading. The local deformations in all directions including the wall thickness, the plasticity and the stress waves at and surrounding the impact point were taken into consideration. The data of the impacting steel missile and the shape of the target concrete wall were given. As the impacting time is short in comparison to the fundamental eigenfrequency of the structure, it is possible to study the local deformation by isolating the impacted zone and its surroundings from the total structure. The boundaries of this region were considered as fully clamped. The results justified this assumption as the stresses at and near the boundaries were negligible in comparison to their counterpart at the impacting point. The PISCES 2 DL code was considered suitable for this type of calculation. Special routines defining the material and yield models for reinforced concrete were integrated in the program system.     

Numerical simulation of high-energy neutron radiation effect of scintillation fiber

Due to their low cost,flexibility,and convenience for long distance data transfer,plastic scintillation fibers (PSF) have been increasingly used in building detectors or sensors for detecting various radiations and imaging.In this paper,GEANT4 Monte Carlo simulation tool was used to obtain some radiation effects of PSF under high-energy neutron irradiation.BCF-20,a plastic fiber material,produced by Saint-Gobain,was used in the simulation.The fiber consists of a core scintillating material of polystyrene and an acrylic outer cladding.Incident neutrons produce energy deposition in fiber through neutron induced recoil proton events.The relationships between energy deposition efficiency and fiber length,fiber radius and incident neutron energy are presented.The variation with those parameters and parameter selection are also analyzed.     

大气压下大功率等离子体炬的数值模拟

主要研究直流等离子体炬的数值模拟方法,通过求解等离子体弧社区域的能量守恒,动量守恒,质量守恒及电流连续性方程,得到不同边界条件下温度,速度,电流密度分布,计算了大气压下２００Ａ自由氩弧的温度分布,电势和电流分布,并与实验数据及现有的理论计算进行了比较,得到了较好的结果,在此基础上结合本实验室５０００Ａ大功率等离子体炬,讨论了有阴极喷口存在下的弧柱部分的数值计算,以及能量守恒方程中辐射项,焦耳热项的     

Numerical simulation of impact of supersonic molecular beam injection on edge localized modes

A three-field model with the impact of supersonic molecular beam injection (SMBI) based on the BOUT++ code is built to simulate edge localized modes (ELMs). Different parameters of SMBI are explored to find an optimal SMBI scenario for ELM mitigation. The linear simulations show that the growth rate of peeling-ballooning mode is reduced by SMBI. The reduction amplitude of the growth rate is increased when the amplitude or width of SMBI is increased, and when SMBI is deposited at the top, bottom and middle of the pedestal, the reduction amplitude increases successively. The nonlinear simulations show that the ELM size is reduced by SMBI. The reduction amplitude of the ELM size is increased when the amplitude or width of SMBI is increased, and when SMBI is deposited at the bottom, top and middle of the pedestal, the reduction amplitude increases successively. Surface-averaged pressure profiles and filamentary structures are analyzed when the ELMs erupt. Deep deposition of SMBI such as at the top and middle of the pedestal reduces the inward collapse amplitude of the pressure profiles, which can improve the confinement efficiency during ELMs. Shallow deposition of SMBI such as at the middle and bottom of the pedestal reduces the outer extent of the filamentary structures, which can slow down the erosion of plasma-facing components caused by ELMs. In conclusion, shallow deposition of SMBI with sufficient amplitude and width can meet the needs of ELM mitigation.     

金属真空弧离子源引出强流离子束的数值模拟

为了引出更高强度、更高亮度的铀离子束,以满足重离子研究中心(Gesellschaft für SchwerionenforschungmbH,GSI)重离子同步加速器的需求,本文用三维的计算机程序KOBRA3-INP对金属真空弧离子源(Metalvapor vacuum arcion source,MEVVA)引出强流铀离子束在引出系统和后加速系统中的动力学特性进行了研究,讨论了离子源发射束流密度对引出束性能的影响.结果表明,束流损失主要发生在引出系统和后加速系统之间的漂移区;在假设漂移区束流被空间电荷中和的情况下,模拟结果和实验结果符合;在发射束流密度为180-230 mA/cm2范围内,经后加速的束流强度变化不大.     

Hard missile impact on reinforced concrete

New penetration, scabbing and perforation formulae are derived for use in the design of reinforced concrete barriers to withstand impact by hard missiles. This is done by using dimensional analysis together with physical theories for the various impact processes. This leads to impact formulae with unknown coefficients which are then determined by an analysis of all available test data. The new formulae so derived are simple and, because of their parametric formulation, have a range of applicability easily definable in terms of impact parameters. The analysis indicates that some recently proposed impact formulae are not safe from the point of view of barrier design because the test data used for their derivation was affected by global movement of the barriers which reduced the measured local damage.     

Model tests of turbine missile impact on reinforced concrete

The results of 25 impact tests on 1/11-scale models of reinforced concrete nuclear plant walls are presented. These tests determined experimentally the maximum velocity at which postulated turbine missiles are contained by typical reinforced concrete walls. The parameters varied were missile weight, velocity, orientation, and impact angle, as well as target design and thickness. The results showed that the NDRC perforation formula used extensively in current practice is overly conservative, whereas a newer empirical formula (CEA-EDF) gave reasonably conservative predictions of the test results. All but the most energetic postulated missiles are stopped by containment wall models, and steel liners on these walls are effective in suppressing backface concrete scabbing.     

Linking of Lagrangian particle methods to standard finite element methods for high velocity impact computations

Lagrangian particle methods, such as smooth particle hydrodynamics, have been developed recently to include the effect of strength, and these techniques have been successfully applied to high velocity impact problems. These methods allow for variable nodal connectivity and can handle severe distortions in a manner comparable with Eulerian codes. The particle methods generally require more computer time than do standard finite element techniques, and are not accurate under some conditions. As a result, there are some advantages associated with linking the particle methods to standard finite elements. If the particle portion of the grid is restricted to those regions that are severely distorted, then the required computer time is reduced and the accuracy may be increased in the standard finite element grid. This paper describes and demonstrates techniques that include attachment, sliding and automatic generation of particles, which are linked to a standard finite element grid. Computed results show good agreement with test data.     

Numerical simulation of boron injection in a BWR

The present study constitutes a first step to understand the process of boron injection, transport and mixing in a BWR. It consists of transient CFD simulations of boron injection in a model of the downcomer of Forsmark’s Unit 3 containing about 6 million elements. The two cases studied are unintentional start of boron injection under normal operation and loss of offsite power with partial ATWS leaving 10% of the core power uncontrolled. The flow conditions of the second case are defined by means of an analysis with RELAP5, assuming boron injection start directly after the first ECCS injection. Recent publications show that meaningful conservative results may be obtained for boron or thermal mixing in PWRs with grids as coarse as that utilized here, provided that higher order discretization schemes are used to minimize numerical diffusion. The obtained results indicate an apparently strong influence of the scenario in the behavior of the injection process. The normal operation simulation shows that virtually all boron solution flows down to the Main Recirculation Pump inlet located directly below the boron inlet nozzle. The loss of offsite power simulation shows initially a spread of the boron solution over the entire sectional area of the lower part of the downcomer filled with colder water. This remaining effect of the ECCS injection lasts until all this water has left the downcomer. Above this region, the boron injection jet develops in a vertical streak, eventually resembling the injection of the normal operation scenario. Due to the initial spread, this boron injection will probably cause larger temporal and spatial concentration variations in the core. In both cases, these variations may cause reactivity transients and fuel damage due to local power escalation. To settle this issue, an analysis using an extended model containing the downcomer, the MRPs and the Lower Plenum will be carried out. Also, the simulation time will be extended to a scale of several minutes.     

Numerical simulation of the transient temperature distribution within the cladding material during annealing in a high vacuum furnace

A high vacuum cylindrical furnace has a load of cylindrical tubes supported by a carriage. The temperature distribution is of particular interest for the industrial annealing of sheaths for nuclear reactor fuel pin cladding. A numerical model is used to calculate the temperatures in the load as a function of time, during both heating and cooling. Theory and experiment agree very well considering the sources of error. Theoretical results were also obtained for the heat transferred between furnace, carriage and tubes, as a function of time. The results allow the design of a complicated high vacuum industrial furnace, and the design and optimization of its loads, to proceed purely by computation.     

Numerical simulation of inducing characteristics of high energy electron beam plasma for aerodynamics applications

The problem of flow active control by low temperature plasma is considered to be one of the most flourishing fields of aerodynamics due to its practical advantages.Compared with other means,the electron beam plasma is a potential flow control method for large scale flow.In this paper,a computational fluid dynamics model coupled with a multi-fluid plasma model is established to investigate the aerodynamic characteristics induced by electron beam plasma.The results demonstrate that the electron beam strongly influences the flow properties,not only in the boundary layers,but also in the main flow.A weak shockwave is induced at the electron beam injection position and develops to the other side of the wind tunnel behind the beam.It brings additional energy into air,and the inducing characteristics are closely related to the beam power and increase nonlinearly with it.The injection angles also influence the flow properties to some extent.Based on this research,we demonstrate that the high energy electron beam air plasma has three attractive advantages in aerodynamic applications,i.e.the high energy density,wide action range and excellent action effect.Due to the rapid development of near space hypersonic vehicles and atmospheric fighters,by optimizing the parameters,the electron beam can be used as an alternative means in aerodynamic steering in these applications.     

Numerical simulation of a free-falling liquid sodium droplet combustion

Droplet combustion is considered one of the combustion figurations in sodium-fire events; the detailed combustion mechanism by which it occurs is evaluated by a developed computational fluid dynamic (CFD) simulation code, called COMET, in which the extended MAC method is employed for calculating the reacting compressible flow coupled with the multi-component diffusion of chemical species. A single droplet combustion in steady-airflow was simulated using the COMET to analyze: (1) the spatial distributions of heat rate and temperature, and (2) the formation, decomposition, and transfer of combustion products. Next, a free-falling droplet combustion experiment was simulated for code validation, where the evaluated falling-velocity and burnt-mass showed good agreement with the experimental values.     

Numerical simulation of impact problems applied to development of spent fuel transport cask for research reactors

Abstract

With the support of the International Atomic Energy Agency, a packaging to transport research reactor irradiated fuel was designed by a trinational team from Argentina, Brazil and Chile. A half-scale model for materials test reactor fuel was constructed and tested according to specifications of regional regulations. Numerical modelling of impact problems played a key role in the cask development. During the design process, it was necessary to improve the performance of the shock absorbers and the containment system. This process was carried out using numerical simulations to predict the behaviour of different shock absorber materials, to consider design improvements and to select the drop orientations. The finite element method was used to simulate the impact problem, and a particular effort was undertaken to model all of the geometrical features with high detail, constitutive equations of different materials and multiple contact problems.     

Numerical simulation of turbulent flow in a 37-rod bundle

The unsteady Reynolds averaged Navier–Stokes equations, combined with a Reynolds stress model, were solved numerically to determine fully developed isothermal turbulent flow in a 60° sector of a 37-rod bundle. It was found that this flow contained large-scale coherent structures, which affected strongly the local velocity fluctuations, especially near the gaps between rods or between rods and the surrounding wall. The time-averaged mean velocity and Reynolds stresses were in good agreement with experimental results in a similar channel. Coherent velocity fluctuations at different locations throughout the entire rod bundle were strongly correlated with each other.     

高分辨电子动量谱仪的能量和动量标定的物理模拟

高分辨电子动量谱仪的能量和动量标定的核心是二维灵敏度位置探测器响应函数在直角坐标系下的正交多项式最小二乘拟合。在谱仪尚未建成的情况下,利用模拟产生用于高分辨电子动量谱仪的能量和动量标定的弹性散射,对标定实验全过程进行了物理模拟。     

反中微子监测反应堆运行的数值模拟

利用反应堆出射反中微子计数监测反应堆运行,是国际上新兴的防扩散监测技术,已经过了实验检验。为研究该方法监测反应堆的能力,我们通过在现有MCNP5和MCORGS数值模拟软件中增加了蒙特卡罗方法模拟出射反中微子数目、能量和方向等信息的功能,开发出了用于模拟探测反应堆运行时出射反中微子的数值模拟软件。利用该软件我们研究了反应堆燃耗与出射反中微子计数关系、不同燃耗下铀和钚材料同位素比与出射反中微子计数关系、不同反应堆运行和换料条件下出射中子随反应堆运行时间的变化规律等问题。数值模拟结果表明,反应堆出射反中微子计数可以提供与反应堆运行情况相关的信息。     

Numerical simulation of the transient temperature distribution inside a close-packed array of cylindrical tubes during heating and cooling under high vacuum

The metallurgical processing of zircaloy for reactor fuel pin cladding requires the annealing of loads, each consisting of an array of tubes in a high-vacuum furnace. A knowledge of the transient temperature distribution in the load during the heating and cooling periods is of interest for the design of the furnace, the design of each load on account of the final yield of the furnace, and the metallurgical control of the process. A general mathematical model was devised, and is presented here, for the numerical simulation of heat transfer by radiation and conduction. The model was used to simulate the behaviour of loads consisting of a close-packed array of cylindrical tubes of two different diameters and wall thicknesses, and in one case with two different surface emissivities. The following processes were simulated: heating from an initial to a final temperature; pre-heating from an initial to an intermediate temperature; final heating from the intermediate to the final temperature, and cooling of the load. Numerous numerical results are presented and discussed in depth in order to get physical insight into the problem, and rules are formulated which are of great value to the engineer and the metallurgist.     

Numerical simulation of the start-up process of a miniature ion thruster

A particle-in-cell Monte Carlo collision model of a discharge chamber is established to investigate the start-up process of a miniature ion thruster. We present the discharge characteristics at different stages (the initial stage, development stage, and stable stage) according to the trend of the discharge current with time. The discharge current is the sum of the sidewall current and the backplate current. During the start-up process, the sidewall current lags behind the backplate current. The variation and distribution characteristics of the discharge current over time are determined by the electron density distribution and electric potential distribution.     

Numerical simulation of a blanket cooling system for fusion reactor based on PWR conditions

The simulations of a blanket cooling system were presented to address the choice of cooling channel geometry and coolant input data which are related to blanket engineering implementation. This work was performed using computer aided design (CAD) and computational fluid dynamics (CFD) technology. Simulations were carried out for the blanket module with a size of 0.6 m × 0.45 m in toroidal plane, and the nuclear heat was applied on the cooling system at P_n (neutron wall load) of 5 MW/m². The structure factors and input data of hydraulics were investigated to explore the optimal parameters to match the PWR condition. It was found that the inlet velocity of first wall (FW) channel should be within the range of 2.48–3.34 m/s. As a result, the temperature rise (TR) of the coolant in the FW channel would be 24–25 K. This leads to the remaining space for TR within the range of 15 K in the piping circuits. It also indicated that the FW plays an important role in TR (reaches 60% of the whole cooling system) due to its high level of P_n and heat flux in the zones. It was predicted that the nuclear heat inside blanket module could be removed completely by the piping circuits with an acceptable pipe bore and the related input data. Finally, a possible design range of cooling parameters was proposed in view of engineering feasibility and blanket neutronics design.