严重事故下吸湿性气溶胶的自然去除研究

反应堆发生严重事故时,堆芯释放出的吸湿性气溶胶会在潮湿的安全壳内增大,从而影响其自然去除过程。本文理论推导了吸湿性气溶胶的增大模型并通过多种方法对其进行了验证。模型计算结果表明,气溶胶的增大过程由于受到溶解度的限制而存在临界湿度值,在该临界值以下时气溶胶不发生吸湿,但这未被其他严重事故分析程序所考虑。同时,基于某三代先进压水堆的特定严重事故工况,本文分析了干颗粒半径及湿度对气溶胶的平衡半径和自然去除系数的影响。结果表明:气溶胶的自然去除系数随干颗粒半径的增大将先减小后增加,并在1 μm时达到最小值;相同湿度下,干颗粒半径对气溶胶半径的最大增大比例的影响不大;湿度的增加对不同干颗粒半径气溶胶去除系数的影响不同。      

鼓泡过滤可溶性气溶胶特性实验研究

池式鼓泡过滤是核电厂严重事故条件下一种重要的放射性气溶胶滞留过程。本文针对可溶性气溶胶在鼓泡过滤条件下的去除特性开展实验研究。结果表明,可溶性气溶胶会在鼓泡过滤过程中吸湿增长,尺寸增大,因此在评价可溶性气溶胶的去除效率时,必须保证上下游气溶胶处于干燥状态;另外,可溶性气溶胶的吸湿增长使得气溶胶的沉降特性发生改变,主要表现为原处于布朗扩散主导区的小粒径气溶胶会进入最易穿透区,效率降低,而原处于最易穿透区的气溶胶会进入惯性主导区,效率增加;气体流量的变化对气溶胶去除效率的影响不是单调的,与气-液两相流型以及气泡行为密切相关。实验结果可为验证和完善池式过滤气溶胶模型提供数据支撑。     

低流速排放下气溶胶水洗模型

在发生核电厂严重事故时,乏池水洗作为放射性气溶胶去除的手段之一,应用于先进非能动压水堆中。为评估气溶胶水洗效果,本文建立了蒸汽冷凝、惯性碰撞、重力沉降、离心沉积和布朗扩散等典型气溶胶去除机制模型,同时考虑了可溶性气溶胶颗粒增大现象,采用FORTRAN语言实现了气溶胶水洗效果分析程序。通过构建LACE Espana实验装置分析模型,模拟了3种典型低流速工况,并开展了气溶胶粒径、蒸汽份额以及淹没深度等关键因素的影响分析。结果表明：水洗净化系数（DF）计算值与实验结果的符合程度合理,模型有效性得到初步验证;DF随气溶胶粒径、蒸汽份额以及淹没深度的增大而增大,可溶性气溶胶颗粒增大将显著提高DF。     

低流速排放下气溶胶水洗模型

在发生核电厂严重事故时,乏池水洗作为放射性气溶胶去除的手段之一,应用于先进非能动压水堆中。为评估气溶胶水洗效果,本文建立了蒸汽冷凝、惯性碰撞、重力沉降、离心沉积和布朗扩散等典型气溶胶去除机制模型,同时考虑了可溶性气溶胶颗粒增大现象,采用FORTRAN语言实现了气溶胶水洗效果分析程序。通过构建LACE-Espana实验装置分析模型,模拟了3种典型低流速工况,并开展了气溶胶粒径、蒸汽份额以及淹没深度等关键因素的影响分析。结果表明:水洗净化系数(DF)计算值与实验结果的符合程度合理,模型有效性得到初步验证;DF随气溶胶粒径、蒸汽份额以及淹没深度的增大而增大,可溶性气溶胶颗粒增大将显著提高DF。     

负载型多分散气溶胶在管道内的传输规律

放射性气溶胶的传输一直是倍受关注的环境问题。为研究放射性气溶胶在管道内的传输规律,首先自制了能够产生稳定的、多分散气溶胶的发生器。主要考察了稀释气流速（5~25 L/min）、气溶胶颗粒粒径（多分散体系）及固体颗粒密度（土壤、石英砂）对气溶胶在管道内传输的影响。即考察了粒径多分散的石英砂、土壤颗粒形成的气溶胶及表面负载Ag的石英砂颗粒模拟负载型放射性气溶胶,在不同稀释气流速作用下进入管道内的传输,针对每一节管道内的沉积物进行收集分析,从而得到气溶胶在管道内的传输及沉降规律。研究结果表明：密闭管道内,在一定流速范围内,沉积物最高频度粒径随着管道距离的增长而先增大后减小;小粒径的颗粒在传输过程中自重沉降,且由于布朗运动吸附在大粒径颗粒物表面加速其沉降速率,即减小了其在管道内的传输距离;表面负载Ag的石英砂颗粒形成的气溶胶随着稀释气吹扫导致Ag和石英砂颗粒之间有不同程度的分凝,气流速率越大,分凝现象越明显。     

固态气溶胶吸湿生长对过滤器检测效率的影响

本文使用加湿串联差分迁移分析仪（HTDMA）系统,研究了荧光素钠气溶胶在不同相对湿度（RH）环境中粒径的变化规律及对现场过滤效率的影响,且与NaCl气溶胶进行了对比。研究结果表明,荧光素钠气溶胶无潮解点,其粒径随相对湿度的增大而增大;NaCl有明显的潮解点,在小于75%相对湿度时,其粒径基本不变。随相对湿度的增加,直径为100 nm的荧光素钠测得的效率逐渐降低,而直径为100 nm的NaCl测得的效率在75%相对湿度以下时基本保持不变,但在大于75%相对湿度环境中大幅下降。因此,从气溶胶吸湿性能的角度来说,作为现场检测用的固态气溶胶,若保证环境相对湿度小于75%,NaCl和荧光素钠均可用于过滤器现场检测,且前者性能优于后者,但当相对湿度大于75%时,NaCl气溶胶已不能用于现场检测用途。     

小冷凝速率下亚微米气溶胶自然沉积实验研究

为了研究小型反应堆在事故后亚微米气溶胶自然沉积行为,自主搭建了实验平台并开展了小冷凝速率下的相关实验。研究中发现蒸汽份额的提升对气溶胶基础的重力沉降过程存在促进作用,压力提升存在抑制作用;泳动去除机制的贡献占比随着蒸汽冷凝速率的提升而增加;冷凝速率较小时,热泳沉积机制在泳动去除机制中的占比可忽略不计;扩散泳S/W模型的适用性提高至385 K,当蒸汽密度和压力再增加时,实验所得亚微米气溶胶的扩散泳沉降速率高于S/W模型预测结果,根据蒸汽冷凝相关理论提出了修正系数。吸湿性气溶胶更容易在蒸汽冷凝条件下被扩散蒸汽夹带去除,3种扩散泳计算模型均无法准确预测吸湿性气溶胶的沉降过程。     

不同送排风方式下铀气溶胶扩散规律模拟研究

本研究基于CFD软件Fluent,开展上送下排、顶送下排、下送顶排、下送上排四种送排风方式下,厂房内铀气溶胶颗粒释放和扩散规律的研究。结果表明,不管哪种送排风方式,厂房内铀气溶胶颗粒的运动轨迹均受到气流组织的影响;顶送下排方式下,部分气溶胶颗粒未排出厂房外,其他送排风方式下,气溶胶颗粒均排出厂房外;下送上排方式下,厂房内污染物平均浓度最低,且排出气溶胶颗粒物的效率最高,其次是上送下排。对于下送上排方式,小粒径颗粒被“包裹”在气流中运动,大粒径颗粒在释放后的初始阶段受气流影响较为明显,但是随着时间推移,颗粒自身惯性力和重力起主要作用。     

华龙一号失水事故后安全壳内气溶胶自然沉降现象研究

对于未采用喷淋系统的安全壳设计,安全壳内的自然沉降过程是放射性核素在安全壳内的一个重要去除机理.本文给出了重力沉降、扩散电泳、热电泳和布朗扩散四种自然沉降机理的沉降速率分析模型,对华龙一号冷管段双端剪切大破口失水事故后安全壳内气溶胶自然沉降现象开展了研究,分析了气溶胶粒径分布特性、气溶胶释放假设对自然沉降现象的影响.分...     

安全壳内放射性气溶胶输运特性模拟研究

为探明实际安全壳尺寸下严重事故中放射性气溶胶的输运特征,利用计算流体动力学和颗粒群平衡方程耦合,模拟了严重事故中放射性气溶胶在安全壳内的空间分布规律,并重点定量分析了不同聚并机制和沉积机制对于气溶胶输运过程的影响。结果表明,粒径小于0.1μm的气溶胶颗粒的相互作用主要受布朗聚并影响,粒径大于10μm的主要受湍流惯性聚并影响,粒径介于两者之间的受布朗聚并和湍流聚并（湍流惯性聚并和湍流剪切聚并）共同影响。对于沉积现象,粒径小于0.1μm的气溶胶主要受布朗扩散沉积影响,粒径大于0.1μm的主要受重力沉积影响。湍流聚并的平均聚并速度是布朗聚并速度的2.99倍,布朗扩散沉积的平均沉积速率是重力沉积的1.38倍。本研究为实际安全壳尺寸下放射性气溶胶去除技术的选取提供了解决思路。     

核反应堆严重事故中气溶胶的吸湿增长研究进展

可溶性气溶胶（以下简称气溶胶）的吸湿增长是影响核反应堆严重事故中放射性产物动力学行为的关键因素之一,本文对吸湿增长的理论模型、实验测量方法以及核安全领域吸湿增长的研究进展进行了总结。核安全领域气溶胶吸湿增长理论模型以K?hler理论为基础,描述了吸湿增长过程中气溶胶热物性等参数与环境参数的关系,在此基础上发展的多种改进模型更适用于实际问题的分析,已在NAUA-HYGROS、MELCOR等核安全气溶胶计算程序中得到广泛应用。实验测量也是研究气溶胶吸湿增长特性的重要手段,相比于可测量气溶胶整体吸湿能力但结果较为粗糙的重量法,电力平衡法、HTDMA法精度较高,且具备实时测量单个颗粒及多模态颗粒群的吸湿能力,在核事故气溶胶吸湿增长特性实验研究方面具有潜在应用前景。本文最后总结了严重核事故领域吸湿增长的现有应用研究,包括核事故典型气溶胶吸湿增长特性的理论模型与数值计算应用研究、吸湿增长实验研究,数值计算研究表明,将气溶胶吸湿增长特性纳入到核事故气溶胶计算程序中可以实现对核事故发生后气溶胶行为更为准确的预测分析,相关实验得到了CsOH、CsI等典型核事故气溶胶的吸湿增长特性。      

Investigation of aerosol kinetics in the protective envelope when analyzing accidental emissions at nuclear plants

The course of an unanticipated accident with serious damage to the core is characterized by the emission of a large quantity of radioactive materials into the first loop and then into the space inside the protective shell. The majority of the fission products enter the protective shell in the form of radioactive aerosols, whose leakage largely determines the consequences of a serious accident. This makes it necessary to model the dynamics of multicomponent aerosols taking account of the coagulation, change of their composition and mass as a result of the condensation-evaporation and dissolution of the gaseous components as well as the precipitation of the particles on different surfaces. A program for calculating the aerosol kinetic during the course of a serious accident is examined.     

Experiments and computational models for aerosol behaviour in the containment

Aerosols generated by condensation of volatile fission products during nuclear reactor core meltdown accidents represent a major fraction of the accidental airborne radioactivity. A comprehensive experimental research programme was performed at Battelle to investigate the transport and deposition behaviour of aerosols in the containment, in order to support the development of computer models which estimate the fission product behaviour in the containment and the source term for potential radionuclide releases to the environment. Important steps in the investigations were: (1) DEMONA experiments. The first large scale aerosol test series performed in the Battelle model containment (BMC) (total volume 640 m³), using an open (quasi one-room) geometry and condensation aerosols from a plasma torch generator. (2) VANAM experiments. Advanced aerosol tests in the BMC, using a multi-room geometry, mixed hygroscopic/non hygroscopic condensation aerosols, a double injection period, and varying thermohydraulic conditions. One of the experiments was subject of the International Standard Problem ISP 37. (3) KAEVER experiments. A systematic investigation of aerosol materials and mixtures and the related deposition behaviour, using a simplified one-room test vessel (10 m³ volume) and advanced instrumentation. Important computer codes developed and/or validated in connection with the experiments are FIPLOC and NAUA; aerosol codes CONTAIN, MELCOR and GOTHIC-MAEROS were also applied. Some important results from the investigations and code developments are: (1) significant local aerosol concentration differences can occur in a multi-room geometry; (2) concentration differences can be caused by atmospheric stratification; and (3) deposition is strongly affected by material hygroscopicity and atmospheric humidity. (4) Satisfactory prediction requires a consistent treatment of multi-room thermal hydraulics, aerosol transport and steam condensation on particles. (5) Prediction results can be affected by numerical stability and nodalization (user experience). This paper presents a number of results of the experimental investigations and the present state of code modelling, with special reference to the findings of ISP37.     

Numerical study on sedimentation behavior of solid particles used as simulant fuel debris

This paper presents numerical simulations using the discrete element method (DEM) to model sedimentation behavior of solid debris particles, which is significant for estimates of the coolability of debris beds. A series of experiments of gravity driven discharge of solid particles into a quiescent water pool was used to validate the DEM simulation method. We evaluated the effects of three crucial factors: particle density, particle diameter, and nozzle diameter on three key quantitative parameters: particle dispersion angle, particle fall time in the pool, and the height of the deposited particle bed to express the particle sedimentation behavior. The three crucial factors play a significant role in the particle sedimentation behavior. We compared the experimental and simulated results of the particle dispersion angle and particle fall time in the pool, and the height and shape of the deposited particle bed. The general trend of the simulation results indicates a reasonable agreement with the experimental observations. The simulations exhibit the potential applicability of the DEM-based simulation technique for the prediction of particle sedimentation behavior.     

Analysis of radionuclide retention in water pools

An analysis is presented of the removal of aerosol particles and gaseous fission products from steam-noncondensable gas mixtures rising through water pools. The pool is divided into a gas injection zone, a bubble rise zone and a pool surface zone. The formulation of the governing conservation equations is relatively general with a quasi-steady one-dimensional formulation for the gas phase, and an unsteady, well stirred, formulation for the liquid phase. An associated computer code for performing the calculations, SUPRA, is described. Results of parametric calculations are given for conditions expected in a BWR severely degraded core accident sequence. Parameters studied include aerosol particle size and distribution, mass fraction of noncondensable gas, gas mass flow rate, quencher submergence depth, and pool water temperature.     

鼓泡过滤多分散气溶胶特性的矩估计分析

池式鼓泡过滤是核电站严重事故场景以及缓解措施中一种典型的放射性气溶胶滞留过程,评估气溶胶在该条件下的去除特性对事故后期的源项评估和制定相应的缓解措施具有重要意义。针对鼓泡过滤多分散气溶胶这一背景,本文假设气溶胶的尺度分布满足对数正态分布,考虑布朗扩散、重力沉降以及惯性碰撞3种机制对气溶胶在气泡内沉降的影响,利用矩方法得到了气溶胶尺度分布的3个分布参数（N、d_pg、σ_g）与其初始值、气泡上升高度以及沉降系数之间的解析关系。通过与精确解对比,对数正态矩方法推导的解析解表现出良好的预测精度。本文得到的解析解可在不需要气溶胶尺度分布具体信息而仅需要一些初始分布参数的情况下对气溶胶的去除特性进行快速评估。