飞机撞击下高温气冷堆乏燃料厂房损伤研究

本文针对典型高温气冷堆乏燃料厂房在双发商用飞机撞击载荷下的响应及结构完整性开展研究,并探讨结构特性对撞击损伤的影响。对乏燃料厂房及飞机分别建立有限元模型,通过弹体-目标相互作用分析模拟了飞机撞击过程,综合IAEA与NRC的评价准则对乏燃料厂房在飞机撞击下的损伤程度进行评估。数值结果表明:厂房上对应于机身及发动机的撞击位置发生可接受的局部损伤;乏燃料贮存井墙体对于提高构筑物抗飞机撞击能力有重要作用。此外,构筑物外形对损伤有很大影响,圆柱形壳体的抗飞机撞击能力显著强于方形厂房,是核电厂厂房设计的优化方向之一。     

高温气冷堆反应堆厂房外墙及蒸发器舱室抗飞机撞击数值分析

反应堆抗大飞机撞击是需要考虑的外部事件,对反应堆的安全评价非常重要。本文在耦合冲击动力学有限元模型的基础上,提出了双层平行墙体承受飞机撞击的等效模拟方法,研究了高温气冷堆（HTGR）较薄的方形蒸发器舱室抗商用飞机撞击能力。建立了反应堆厂房外墙受商用飞机撞击穿透评价标准,并进行了商用飞机撞击反应堆厂房外墙仿真计算,得到了飞机剩余动能曲线。飞机撞击蒸发器舱室的计算中,保守假设飞机穿过外墙后无质量损失,形态完好,以剩余速度撞击方形蒸发器舱室。评估表明,蒸发器舱室结构在撞击条件下的整体损伤微小,可为保护内部关键设备提供重要的屏障功能。      

飞机撞击核岛屏蔽厂房的有限元分析

采用经典的显式有限元动力程序LS-DYNA,模拟商用大型飞机对核岛屏蔽厂房的撞击,混凝土有限元动力模型采用Holmquist-Johnson-Cook模型,用来模拟混凝土在大应变、高应变率下的非线性性能,同时评估屏蔽厂房的抗飞机撞击能力。     

基于Octree-SBFEM跨尺度模型的大型商用飞机撞击核电厂的精细化损伤演化分析

采用比例边界多面体有限元分析方法，结合八分树网格离散技术，开展了第三代核电厂在大型商用客机撞击下屏蔽厂房的损伤演化分析，讨论了基础效应、撞击区域形状选取和结构-地基相互作用的影响。结果表明:比例边界多面体有限元分析方法具有极强的网格离散能力、单元质高量少，且对模型修改有极高的适应性，与传统方案相比，效率可提高几十倍；精细化模型更准确地模拟了损伤演化与渐进破坏过程；飞机撞击核岛分析中的基础效应及结构-地基相互作用（SSI效应）在非岩性地基时不可忽略。      

高温气冷堆舱室抗商用飞机撞击的耦合数值分析

本文建立了大型商用飞机撞击典型高温气冷堆核电站反应堆舱室的非线性有限元模型，计算中混凝土舱室直接采用工程用钢筋混凝土的损伤塑性本构模型，飞机结构采用Johnson-Cook本构模型。对飞机高速撞击高温气冷堆核电站反应堆舱室非线性撞击过程进行模拟计算，得出正面和侧面撞击条件下的撞击载荷曲线、撞击位移云图、反应堆舱室混凝土破坏情况等结果。评估表明，反应堆舱室结构在撞击条件下的整体损伤微小，可为保护内部关键设备提供重要的屏障功能。     

乏燃料运输事故中放射性物质的释放机制及途径

符合国际原子能机构《放射性物质安全运输规定》要求的乏燃料运输容器,具有相当高的抗事故能力。但在运输过程中,仍有可能出现超过容器设计基准的冲撞(撞车、撞击山体或其它构筑物)、翻车、火灾等事故,导致乏燃料组件及其运输容器受损,向环境释放出放射性物质;或者导致运输容器屏蔽能力减弱乃至丧失,使意外接近容器的人员或公众受到较高水平的外照射。     

美国核电厂容纳核燃料的构筑物可承受飞机撞击

【美通社华盛顿2002年12月23日电】美国电力研究所(EPRI)过去几个月进行的分析表明,即使受到大型商用喷气客机的撞击,美国核电厂中容纳核燃料的构筑物也可保证不会发生辐射泄漏事故。 这次独立研究是应美国核能研究所(NEI)的要求,在美国能源部(DOE)的资助下完成的,耗资约100万美元。 最新的计算机模拟结果表明,美国核电厂使用的乏燃料贮存水池、乏燃料贮存容器和乏燃料运输容器的安全壳结构可承受客机撞击之类的外力影响,尽管某些部位会发生混凝土破碎和钢筋弯曲现象。 此次分析使用了能够增加分析保守性的几个场景。其中最引人注目的假…     

高温气冷堆舱室抗商用飞机撞击的耦合数值分析

本文建立了大型商用飞机撞击典型高温气冷堆核电站反应堆舱室的非线性有限元模型,计算中混凝土舱室直接采用工程用钢筋混凝土的损伤塑性本构模型,飞机结构采用Johnson-Cook本构模型。对飞机高速撞击高温气冷堆核电站反应堆舱室非线性撞击过程进行模拟计算,得出正面和侧面撞击条件下的撞击载荷曲线、撞击位移云图、反应堆舱室混凝土破坏情况等结果。评估表明,反应堆舱室结构在撞击条件下的整体损伤微小,可为保护内部关键设备提供重要的屏障功能。     

AP1000钢筋混凝土屏蔽厂房抗大型商用飞机撞击分析

针对建设中的三门、海阳AP1000钢筋混凝土(RC)屏蔽厂房,开展抵抗大型商用飞机撞击的分析研究。分析中采用我国核安全导则(HAD)推荐的总质量约90 t的大型窄体商用飞机作为撞击飞机,选取屏蔽厂房筒身中部、进气口区域和屋顶锥屋面作为撞击目标,并采用LS-DYNA显式有限元分析软件使用"飞机-标靶相互作用法"进行3种工况模拟。结果表明:AP1000的RC屏蔽厂房可以抵抗这种级别飞机的撞击。     

基于ANSYS/LS-DYNA的抗飞机撞击结构非线性动力分析

APC壳是核电站抵御飞机撞击的主要屏障,本文运用非线性有限元程序LS-DYNA对某核电站燃料厂房APC壳进行了分离式建模,并对大型商用飞机的撞击进行了数值计算,对APC壳的动力响应及弹塑性特性进行了研究分析,提出了大型商用飞机撞击局部效应的观点,为APC壳的设计计算提供参考。     

Finite element analyses and verifying tests for a shock-absorbing effect of a pad in a spent fuel storage cask

A spent fuel storage cask is required to prove the safety of its canister under a hypothetical accidental drop condition which means that the canister is assumed to be free dropped on to a pad of the storage cask during the loading of the canister into a storage cask. In this paper, finite element analyses and verifying tests for a shock-absorbing effect of a pad in a spent fuel dry storage cask were carried out to improve the structural integrity of the canister under a hypothetical accidental drop condition. The pad of the storage cask was originally designed as cylindrical steel structure filled with concrete. The pad was modified by using the structure composed of steel and polyurethane-foam instead of the quarter of the upper concrete as an impact limiter. The effects of the shape and the thickness of the steel structure and the density of the polyurethane-foam which was used in between steel structures were studied. As the optimized pad of a spent fuel dry storage cask, the quarter of the upper concrete was replaced with 12 mm thick circular steel structure and polyurethane-foam whose density was 85 kg/m³. The drop tests of a 1/3 scale model for the canister on to the original pad and the optimized pad were conducted. The effect of the pad structure was evaluated from the drop tests. The optimized pad has a greater shock-absorbing effect than the original pad. In order to verify the analysis results, strains and accelerations in the time domain by the analytical methods were compared with those by a test. The numerical method of simulating the free drop test for a dry storage cask was verified and the numerical results were found to be reliable.     

A Numerical Analysis for a BWR Fuel Assembly Drop Event

A BWR fuel assembly dropped from the crane hook during outage and clashed against the rack bottom plate of spent fuel pool. The area monitoring system indicated no radiation release, however, damage at the top of fuel channel was found in the following inspection. As fuel integrity is essential for further management, a finite element model was established to evaluate the damage condition. Several component elements including fuel rods, tie plates, and channel were set up and integrated into a full assembly. The analysis results provided the impact force on the fuel assembly and the dynamic response of each component element. The event did result in the damage of fuel channel yet fuel rods fracture was not expected. It's consistent with the inspection observations. There is therefore no concern for future operation such as interim dry storage.     

Structural integrity analysis of an Ignalina nuclear power plant building subjected to an airplane crash

Recent terrorist attacks using commandeered commercial airliners on civil structures have raised the issue of the ability of nuclear power plants to survive the consequences of an airliner crash. The structural integrity analysis due to the effects of an aircraft crash on an Ignalina nuclear power plant (INPP) accident localization system (ALS) building is the subject of this paper. A combination of the finite element method and empirical relationships were used for the analysis. A global structural integrity analysis was performed for a portion of the ALS building using the dynamic loading from an aircraft crash impact model. The local effects caused by impact of the aircraft's engine on the building wall were evaluated independently by using an empirical formula.The results from the crash analysis of a twin engine commercial aircraft show that the impacted reinforced concrete wall of the ALS building will not have through-the-wall concrete failure, and the reinforcement will not fail. Strain-rate effects were found to delay the onset of cracking. Therefore, the structural integrity of the impacted wall of the INPP ALS building will be maintained during the crash event studied.     

高燃耗对乏燃料贮存和运输的影响研究

本文对高燃耗对乏燃料包壳结构完整性的影响进行了分析。探讨了影响包壳结构完整性的重要温度限值,即燃料包壳温度限值、包壳溶解温度以及韧脆转变温度(DBTT)。给出了分析包壳结构完整性的方法,对拟在干式贮存设施内贮存超过20年的容器性能及贮存后运输时乏燃料组件的结构完整性进行了分析,并给出了相关建议。     

A methodology for the evaluation of fuel rod failures under accident conditions

Abstract

Recent studies on the long-term behaviour of high-burnup spent fuel have shown that, under normal conditions of storage, challenges to cladding integrity from various postulated damage mechanisms, such as delayed hydride cracking, stress-corrosion cracking and long-term creep, would not lead to any significant safety concerns during dry storage, and regulatory rules have subsequently been established to ensure that a compatible level of safety is maintained. However, similar regulatory rules have not yet been developed to address failures of fuel rod cladding that could potentially lead to reconfigured fuel geometry under hypothetical transport accidents. At issue is the effect on cladding ductility of potential changes in zirconium hydride morphology during dry storage. Recent studies have shown that above a certain level of cladding hoop stress, the decaying temperature history during dry storage can cause the hydrogen in solid solution to precipitate in the form of radial hydrides, which, depending on their relative concentration, can induce brittle failures in the cladding. From a US regulatory perspective such cladding failures, if they were to cause fuel reconfiguration, could invalidate the cask's criticality and shielding licensing analyses, which are based on coherent geometry. This paper describes a methodology for high-burnup spent fuel to determine the frequency of cladding failure and failure modes under drop accidents, considering end-of-storage spent fuel conditions. The degree to which spent fuel reconfiguration could occur during handling or transport accidents would depend to a large extent on the number of fuel rod failures and the type and geometry of the failure modes. Such information can only be developed analytically, as there are no direct experimental data that can provide guidance on the level of damage that can be expected. To this end, this paper focuses on the development of a methodology for modelling and analysis that deals with this general problem on a generic basis. First, consideration is given to defining accident loading that is equivalent to the bounding hypothetical transport accident of a 9 m drop onto an essentially unyielding surface. Second, an analytically robust material constitutive model, an essential element in a successful structural analysis, is required. A model of material behaviour, with embedded failure criteria, for cladding containing various concentrations of circumferentially and radially oriented hydrides has been developed and implemented in a finite-element code. The hydride precipitation model, which describes the hydride structure of the cladding at the end of dry storage, and the hydride-dependent properties of high-burnup fuel cladding form the main input to the constitutive model. The third element in the overall process is to utilise this material model and its host finite-element code in the structural analysis of a transport cask subjected to bounding accident loading to calculate fuel rod failures and failure mode configurations. This requires detailed modelling of the transport cask and its internal structure, which includes the canister, basket, fuel assembly grids and fuel rods. The overall methodology is described.     

压水堆核电厂乏燃料组件源项计算分析

核燃料贮存、运输以及后处理过程中的安全是构成核与辐射安全的重要内容,为保证安全性,提高运输经济性,减小后处理厂对环境的排放,须获得乏燃料组件的包络源项,因此,采用ORIGEN-ARP程序分析组件运行历史、初始富集度、燃耗深度等参数对源项的影响。运行历史在卸料初期对源项略有影响,可采用合适的保守因子予以包络,在冷却一定时间后,其影响可忽略不计;初始富集度、燃耗深度均不同的组件须经对比计算以获得包络源项。计算表明：在目前核电厂乏燃料组件中,²³⁵U初始富集度为4.45%、燃耗深度为55 GW•d/tU的AFA-3G型组件源项是包络的,可作为乏燃料水池、运输容器设计,以及后处理厂排放源项分析的初始源项。     

Safety Margins of Spent Fuel Transport and Storage Casks Considering Aircraft Crash Impacts

Abstract

The safety of spent fuel transport casks in severe accident conditions is always a matter of concern. This paper surveys German missile impact tests that have been carried out in the past to demonstrate that German cask designs for transport and interim storage are safe even under conditions of an aircraft crash impact. A fire test with a cask beside an exploding propane vessel and temperature calculations concerning prolonged fires also show that the casks have reasonably good safety margins in thermal accidents beyond regulatory fire test conditions.     

海洋核动力平台乏燃料贮存格架设计及安全分析研究

针对海洋核动力平台乏燃料组件海上长期贮存所面临的安全保证问题,通过改进燃料组件与贮存小室之间固定形式、优化贮存小室与贮存格架本体之间连接形式以及增加贮存格架与乏燃料水池池壁之间的缓冲结构,设计了一种满足设计基准以及适应海洋环境的乏燃料贮存格架,并采用蒙特卡罗程序MCNP-5、计算流体力学软件Fluent 14.0、有限元分析软件ANSYS 17.0对该贮存格架进行临界、热工、结构仿真计算。结果表明,该贮存格架设计合理、安全性高,可为海上浮动式核电站乏燃料贮存提供解决方案。      

Effect of irradiation on the impact and seismic response of a spent fuel storage and transport cask

The spent fuel storage and transport cask must withstand various accident conditions such as fire, free drop and puncture in accordance with the requirement of the IAEA and domestic regulations. The spent fuel storage and transport cask should maintain the structural safety not to release radioactive material in any condition. And also the effects of the irradiation should be considered because the spent fuels stored in the cask for a long time and be possible to change the mechanical properties of the cask.In this study, the changed mechanical properties of the cask after irradiation for the 30 years storage periods are assumed and applied to the impact analysis using ABAQUS/Explicit code and seismic analysis using ANSYS code. The stress intensity on each part of the cask is calculated and the effects of irradiation are studied and structural integrity of the package is evaluated.