CEFR放射性钠火风险分析

对CEFR的研究发现,一回路外的钠净化管道或阀门破裂将导致放射性钠火事故发生,其中309/1设备间的泄漏后果最严重。采用概率安全评价技术对该事故进行放射性风险分析,依据钠泄漏及钠火发生后相关系统的响应特性,确立了44个事故序列,建立了事件树-故障树模型。对模型进行定量分析     

8 CEFR放射性钠火风险分析

对CEFR的研究发现，一回路外的钠净化管道或阀门破裂将导致放射性钠火事故发生，其中309／1设备间的泄漏后果最严重。采用概率安全评价技术对该事故进行放射性风险分析，依据钠泄漏及钠火发生后相关系统的响应特性，确立了44个事故序列，建立了事件树．故障树模型。对模型进行定量分析后获得了该事件的厂内、外放射性风险，并通过对计算结果的分析，找出风险支配性因素，相应提出降低风险的措施。在整个分析过程中应用了概率安全分析软件、池式钠火分析程序及高架点源气溶胶扩散程序，获得了事故序列发生频率、钠气溶胶排放量、各种情况下高架烟囱周围3公里范围内的剂量分布等定量分析指标。     

中国实验快堆钠火消防系统的可靠性评价研究

作为我国第一座钠冷快中子堆,中国实验快堆(CEFR)的安全问题一直受到广泛关注,其中钠火相关安全问题更成为业界关注的焦点。本文以CEFR一回路冷阱工艺间发生钠火事故时,消防和相关事故缓解系统的可靠性评价为主要任务,运用事件树和故障树相结合的方法,对钠火事故的发生序列及后果进行分析,评价结果表明:CEFR钠工艺间的钠火消防系统具有较高的可靠性。在系统及部件重要度的定性和定量分析结果的基础上,进一步针对钠火消防系统设计的薄弱环节提出钠火消防的优化建议和措施。     

钠冷快堆钠火概率安全评价方法研究

钠火事故是钠冷快堆的典型和特有事故,且很可能是反应堆总风险的主要贡献因素之一。本文在介绍钠火事故特点的基础上,研究使用概率安全分析评价钠冷快堆钠火风险的方法。以中国实验快堆反应堆大厅钠火事故为实例,计算得到反应堆大厅钠火导致的堆芯损坏频率为1.19×10^-8/(堆•年)。在此基础上进一步讨论目前钠火概率安全评价中尚需研究的关键问题。     

CEFR一回路管廊通风系统改造后雾状钠火事故分析

中国实验快堆（CEFR）是液态金属钠冷却的快中子实验堆,一回路钠净化系统管廊即309/1房间作为放射性钠气溶胶包容小室之一,房间内布满高温涉钠管道,特别是布置了反应堆主容器内高温强放射性钠流向外部的唯一管道。假使管道破裂,SSW喷射出的高温钠会燃烧引起钠火,在一定条件下,可能会产生持续的雾状钠火,对于房间压力、房间内气体温度、内部结构温度等因素影响很大。基于给309/1房间降温的目的对该房间进行了通风系统改造,改造后的通风系统增大了在309/1房间的正常排风量和正常进风量,这应该会对309房间的钠火事故热力学后果有所影响。本文利用FEUMIX程序计算一回路管廊通风系统改造后发生的雾状钠火事故后果,并与原通风设计条件下的雾状钠火事故后果进行对比,结果表明,通风系统改造对一回路管廊的雾状钠火事故具有一定缓解效果。     

钠工艺间钠雾火模型适用性分析

钠冷快堆钠泄漏事故中,泄漏的钠以液滴形式在抛射过程中与空气剧烈反应,发生钠雾火现象。通过桑迪亚国家实验室（Sandia National Laboratories,SNL）的T3钠雾火实验结果,以及原子国际（Atomics International,AI）的J1～J4钠雾火实验结果,对改进的Tsai钠雾火模型适用性进行了评估。针对Tsai模型高估实际工况钠喷雾燃烧速率的问题,将Tsai模型中钠液滴下落模型改为单一速度模型,同时将喷雾燃烧对空间的影响改为瞬发。在T3实验中分析了钠雾火阶段对改进模型适用性的影响,在J1～J4实验中分析了初始氧气浓度对改进模型适用性的影响。结果表明：改进的钠雾火模型能够很好地预测空气中钠喷雾燃烧的升温升压现象以及钠消耗量,可以应用于预测钠工艺间内钠泄漏事故后发生在空气中的钠雾火行为。     

钠冷快堆钠雾火事故三维数值模拟

针对钠冷快堆可能发生的钠雾火事故,开发和研制了一套用于钠火事故分析,能求解发生钠雾火事故后,事故空间3维的气体温度分布和化学成份分布的程序。本文详细介绍了分析求解钠雾火的燃烧模型和热传输模型,以及计算空间流场采用的计算方法和步骤,并将计算结果与试验值进行了比较：结果表明,二者符合较好。     

池式钠冷快堆双层容器泄漏事故序列研究

钠冷快堆是第4代反应堆中的优选堆型,具有安全性高的特点。池式钠冷快堆的双层容器泄漏会导致一回路钠泄漏并发生严重事故。本文采用概率安全分析方法分析池式钠冷快堆双层容器泄漏事故,包括事故的确定论分析及放射性释放路径分析以及池式钠冷快堆双层容器泄漏的事故序列及定量化。结果表明,池式钠冷快堆双层容器泄漏事故后正常通风开启情况下可能发生大量放射性释放。双层容器泄漏导致的大量放射性释放频率为1.07×10^-11（堆•年）^-1,双层容器泄漏事故中大量放射性释放占比为0.1%。     

百万千瓦级压水堆核电厂二级PSA源项分析与研究

为解决源项分析中存在的问题,使用严重事故一体化软件进行详细的计算分析,给出百万千瓦级压水堆核电机组各释放类的源项释放结果。针对代表性事故序列选取这一关键技术问题,进行敏感性分析,结果表明,代表性事故序列的选取方法应尽可能从概率代表性的角度,选取释放类中发生概率最高的事故序列。此外,释放途径模拟、水洗对放射性产物的去除作用对计算结果影响较大,应进行详细模拟。     

池式钠火事故下燃烧产物气溶胶行为研究

在钠冷快堆的安全评估中,分析钠泄露导致的池式钠火事故下燃烧产物的气溶胶行为尤为重要。本文采用将池式钠火燃烧模型与气溶胶动力学模型耦合的方式,开发了池式钠火事故下燃烧产物气溶胶行为分析程序REBAC-SFR,基于该程序模拟了SAPFIRE-D1和ABCOVE池式钠火实验,并与实验数据进行了对比。结果表明,本文开发的程序具有良好的可靠性和正确性,可为钠工艺间内池式钠火事故下燃烧产物气溶胶行为分析研究提供理论工具。      

Study on construction of loss of component cooling water system initiating event fault tree for fire event PSA

ABSTRACT

In this study, the construction of the loss of component cooling water system (LOCCWS) initiating event (IE) fault tree (FT) for an actual fire event probabilistic safety assessment (PSA) model of the Korean reference nuclear power plant considering only IE initiators was validated. The quantification results of the LOCCWS accident sequences obtained using an LOCCWS IE FT model with only initiators are similar to that with initiators and enabling events. This confirmed that the LOCCWS IE FT for an actual fire event PSA model could be constructed by considering only IE initiators. In addition, the same LOCCWS accident sequences were quantified assuming that fire triggering only the LOCCWS IE leads to reactor shutdown. Compared with the quantification result obtained based on the assumption that any fire included in the fire event PSA leads to reactor shutdown, the core damage frequency (CDF) can be reduced. Thus, it can be concluded that there is a possibility of underestimation of CDF when the LOCCWS IE FT model with only initiators is used and the assumption that fire triggering only the LOCCWS IE results in reactor shutdown is employed for the quantification of LOCCWS accident sequences.     

基于FDS程序的钠火事故情景模拟技术研究

钠火是钠冷快堆的典型事故,钠火事故情景计算机模拟仿真是对钠火事故风险评价的有力工具。本文以常规火灾三维计算流体力学软件FDS为平台,增加钠火燃烧模型,包括燃烧热模型、燃烧速率模型、喷射液钠粒径分布模型等,完成了钠火情景模型的开发,并通过与SPHINCS钠火试验和计算结果的温度分布与氧气含量对比,验证了模拟技术和模型开发方案的可行性。本文的研究成果能为后续钠火仿真模拟程序的开发提供研究基础和经验参考。     

Sodium Fire Accident Scenario Simulation Technology Study Based on FDS Code

Sodium fire is a typical accident of sodium-cooled fast reactor. Simulation of sodium fire accident scenario by software is a powerful tool for risk assessment of sodium fire accident. In this paper, the conventional fire three-dimensional computational fluid dynamics software FDS was used as a platform to add a sodium fire combustion model, including combustion heat model, combustion rate model, spray liquid sodium particle size distribution model, etc., and complete the development of sodium fire scenario modeling analysis program. And through the comparison with SPHINCS sodium fire test and calculation results, the feasibility of the method and development plan was verified. The research results of this paper can provide the research basis and experience reference for the development of the subsequent sodium fire simulation program.     

Establishment of risk-based accident scenarios using the master logic diagram related to LILW management in the temporary storage facility

The initiating event, which is the first step in the establishment of risk-based accident scenarios, was derived by master logic diagram (MLD) method based on the fault tree analysis (FTA), and then the risk-based accident scenarios were developed by the event tree analysis (ETA) through the derived initiating events. The main initiating events led to the arbitrary operational accident: the dropping of a drum and fire were derived from the MLD method. Consequently, based on two main initiating events, four heading events were derived, and then the 12 risk-based accident scenarios concerning the LILW management in the temporary storage facility were finally established by the ETA method.     

严重事故下蠕变诱发RCS破裂的概率评估

严重事故下一回路管道可能会发生蠕变失效,若出现蠕变诱发的蒸汽发生器传热管破裂（SGTR）,则会导致安全壳旁路失效;若出现蠕变诱发热段或波动管的失效,则产生的破口将会使一回路迅速卸压。因此,评估严重事故下蠕变诱发反应堆冷却剂系统（RCS）破裂的可能性是开展严重事故分析、特别是二级概率安全分析（PSA）的重要基础。本工作基于蠕变失效模型,考虑传热管的缺陷,建立了评价蠕变诱发RCS破裂的确定论模型。在此基础上,运用拉丁超立方体抽样方法,考虑重要参数的不确定性,开发了严重事故下蠕变诱发RCS破裂的概率评估程序。随后对典型的事故序列进行了蠕变诱发RCS破裂的概率评估。结果表明,对于高压事故序列,存在一定的蠕变诱发SGTR概率,也存在较高的蠕变诱发热段或波动管失效概率。     

Comparison of UF6 packages under certification test and accident conditions

Abstract

Currently there are three packages approved by the NRC for US domestic shipments of fissile quantities of UF₆: NCI-21PF-1, UX-30, and ESP30X. For approval by the NRC, packages must be subjected to a sequence of physical tests to simulate transportation accident conditions as described in 10 CFR part 71. The primary objective of this project was to compare conditions experienced during these tests to conditions potentially encountered in actual accidents and to estimate the probabilities of such accidents. Comparison of the effects of actual accident conditions to 10 CFR part 71 tests was achieved by means of computer modelling of structural effects on the packages due to impacts with actual surfaces, and thermal effects resulting from tests and other fire scenarios. In addition, the likelihood of encountering bodies of water during transport over representative truck routes was assessed. Modelled effects and their associated probabilities, accident rates, and other characteristics gathered from representative routes were combined with existing event tree data to derive generalized probabilities of encountering accident conditions comparable to or exceeding the 10 CFR part 71 test conditions. This analysis suggests that the regulatory conditions are unlikely to be exceeded in real accidents.     

钠冷快堆混合钠火程序开发

钠管道泄漏继而发生钠的燃烧为钠冷快堆特有的事故。在喷雾钠火模型和池式钠火模型基础上,将钠喷雾燃烧和池式燃烧进行了耦合,并针对钠冷快堆钠工艺间的结构特点,最终开发了混合钠火计算程序COMSFIRE。使用该程序计算了FAUNA喷雾钠火试验和CADARACHE池式钠火试验,并与试验结果和部分程序计算结果进行了对比。同时设计了混合燃烧算例,并使用该程序与CONTAIN-LMR程序进行了对比。通过计算结果的对比和分析,初步验证了程序的正确性。     

Development of Sodium-cooled Fast Reactor Sodium Combined Fire Code

Sodium fire caused by sodium pipe leakage is the specific accident for sodium-cooled fast reactor. Based on the sodium spray fire model and sodium pool fire model, sodium spray fire and sodium pool fire were coupled together. A sodium combined fire code COMSFIRE was finally developed based on the structure characteristic of sodium technology room in sodium-cooled fast reactor. FAUNA sodium spray fire experiment and CADARACHE sodium pool fire experiment were calculated with the developed COMSFIRE code, the results of which were compared with the experiments results and some other code results. A combined fire case was designed, and the results were compared with CONTAIN-LMR code. The correctness of the COMSFIRE code was primarily proved through the comparison and analysis.     

CONTAIN-LMR程序中池式钠火事故分析计算模型的验证

CONTAIN-LMR是针对以液态钠为冷却剂的反应堆而开发的安全壳事故一体化分析程序。我国目前的CONTAIN-LMR程序版本为2000年左右从法国引进,还未进行过面向工程设计的系统性地程序开发和验证。本文主要针对CONTAIN-LMR程序中模拟池式钠火事故的分析模型进行详细分析,并采用国际上的池式钠火实验进行验证,实验验证结果表明CONTAIN-LMR程序可以较准确地模拟池式钠火事故造成的钠工艺间内的温度、压力升高及放射性钠气溶胶行为。本文的研究结果初步表明CONTAIN-LMR程序可用于钠冷快堆的钠火事故分析。