中国实验快堆燃料组件频率测量试验

堆芯的安全性极其重要,反应堆堆芯组件的抗震分析比较困难。为给中国实验快堆堆芯组件的数值分析提供依据,同时也为安全审评提供基本数据,利用动态测量系统完成了单根燃料组件分别在空气和水介质中频率的测量。试验中,分别采用了3档不同幅值的激励力。考虑安装公差对频率的影响,采用重新安装燃料组件的方法重复测量。经分析,试验结果合理可靠。     

Hidex 300SL液闪装置测量低水平氚水活度的参数优化

Hidex 300SL是基于三管符合计数/两管符合计数(TDCR)方法绝对测量低水平氚水活度的液闪装置。本工作基于该装置对标准非淬灭氚水样品进行测量研究,明确了系统的探测效率与TDCR的关系;讨论了该装置的测量模式、符合时间等参数对计数率、衰变率和TDCR的影响;并对仪器的运行参数进行选择优化,在"H-3"测量模式及35ns的符合时间窗下,系统对3 H的探测效率达73.2%,衰变率稳定性好于0.47%;最后对空气本底样品进行测量,评估了该装置对氚水样品的探测下限,为后续环境低水平样品的精确测量提供有益参考。     

基于抽样的不确定性及敏感性分析的方法在核电厂水膜蒸发试验误差分析中的应用

与传统的误差分析方法相比,基于抽样的不确定性及敏感性分析具有较大的优势。本工作通过耦合DAKOTA程序和水膜蒸发试验数据分析程序,开发了水膜热态试验误差分析方法,计算得到了试验目标参数水膜蒸发换热乘子的不确定性范围,并且分析了试验测量参数的不确定性对蒸发换热乘子不确定性的影响。计算结果表明,水膜入口流量、入口风速以及平板表面温度是主要的不确定性来源。这为优化试验测量系统,减小试验误差提供了定量支持。该方法可以用于其他试验误差分析以及参数重要性分析。     

医用电子加速器高能光子水吸收剂量溯源

采用直接法测量医用电子加速器高能光子水吸收剂量,与我国现行的从空气比释动能转化为水吸收剂量间接法测量的结果进行比较。结果表明,两种方法测量结果相差1%以内,同时用传递比较法进行了验证。证明我国基于加速器光子水吸收剂量基准而建设的水吸收剂量溯源体系是可行的,为我国水吸收剂量直接测量提供依据。     

应用MELCOR对FPT1棒束失效过程的模拟分析

应用MELCOR1.8.6程序对严重事故试验PHEBUS-FPT1进行了模拟分析.通过对棒束毁损过程中涉及的燃料棒过热、锆水反应、裂变产物释放和迁移、燃料熔融坍塌等现象和机理的建模计算,得到的结果和趋势与试验测量值进行了比较分析.分析结果表明:计算得到的棒束失效过程中发生重要事件与试验值较吻合;表征严重事故过程的重要现象--锫水反应所产生的氢气趋势,计算值与试验值比较一致;棒束栅元单一控制体划分,会使得计算得到的燃料峰值温度等表征严重事故来临时间晚于试验值;用CORSOR-M模型预测得到的大部分裂变产物核素释放总量要低于试验测量值,并且该模型较高的估计了氧化热对Xe、Cs、I、Te等易挥发核素释放的影响.     

旋叶汽-水分离器空气-水冷态试验研究

采用可视化的实验方法研究旋叶汽-水分离器的空气-水分离过程和分离性能。试验表明:旋转通道上方形成均匀稳定且厚度适中的液膜有利于气-液两相的分离。水流量较小时,液滴形态的水比例较高,难以分离;而水流量较大时形成液膜较厚,中心空气流通截面变小导致空气夹带水加剧。分离效率的定量测量结果与可视化结果一致。分离效率主要受到水流量的影响,随着水流量的增大逐渐上升,当水流量增大到0.3m3/h后增加趋势逐渐减缓进而呈下降的趋势。     

反应堆堆内构件动态特性试验研究分析

介绍了反应堆试验模型主要部件在空气中和静水中进行的动态特性试验,包括所用的测量系统、试验原理、试验方法和得到的试验结果。并对试验结果进行了分析,说明了试验结果的合理性。     

压水堆松动件故障监测中水对碰撞波影响的研究

应用噪声分析技术，对模拟松动件的碰撞分别发生在空气中或水中，而被碰撞钢板的上，下边界分别为空气或水的几种情况进行了试验，研究水对碰撞波产生和传播的影响，测定了碰间测定的时间波形和平均功率谱，通过对实验结果的比较与分析得出：当碰撞发生在水中时，响应加速度的最大幅值，衰减速度才平均功率谱分布等与在空气中相比，都有明显的不同。研究结果表明，在压水堆松动件监测中采用美国学者Ｗ．Ｈ．ＨｏｐｐｍａｎｎⅡ提出的     

氡子体多段测量法

在用多段法测量空气中氡子体浓度时,增加测量段数可以减小测量误差。本文对段数大于8的多段测量法的测量条件的选择进行了探讨,给出了较好的采样时间、段数、分段方法和测量时间,并通过实验与 Thomas 三段法进行了比较。     

大功率压水堆PCS水分配试验系统设计与实现

针对大功率非能动安全壳基准事故下的水流特征,采用和原型安全壳相同尺寸比例及切片形式,设计了椭球扇面试验台架装置和相应的测量系统以研究安全壳穹顶水膜覆盖率和延迟时间等关键参数与冷却水流量之间的关系。同时开发了大空间曲率表面的视频测量系统,通过电容探针及其三维可调节支架系统实现了本体各处的水膜厚度非接触式测量,并对关键测量系统进行了标定。初步分析结果表明,试验本体及回路设计合理可行,获得了水膜覆盖率和相对延迟时间随雷诺数的变化关系。     

竖直管内两相流逆向流动特性研究

实验发现在竖直管内两相流逆向流动过程中,由于气体的入口条件不同、淹没开始点可能出现在气相的入口处,也可能出现在出口处。由于出现的位置不同,淹没开始点所对应的气、水之间的关系式也不一样。这一实验结果对进一步研究淹没开始的机理有重要意义。根据两相流的流动特性,分析了出现这种现象的原因,提出应采用不同的关系式计算这 两种不同的淹没开始点。     

Study of countercurrent flow limitation in a horizontal pipe connected to an inclined one

Experiments with air and water in small hot leg reproductions were carried out aiming to acquire a better understanding of the countercurrent flow limitation (CCFL) in this geometry. The effects of various geometrical parameters of the test section and of the inlet water flow rate on the onset of flooding, on the partial delivery of water and on the zero liquid penetration were investigated. It was observed that while the onset of flooding is affected by the inlet water flow rate, the zero liquid penetration is independent of this flow rate. The results with partial delivery showed that, for a fixed air velocity, an increase in the horizontal length, or in the inclined length, of the flow channel leads to an increase of the water carried over by the air. On the other hand, in pipes with larger diameters the drag of the water is smaller. The experimental results showed small differences in the results for tests with inclination of the riser lower than 90°. For an inclination equal to 90°, the water carried by the air tends to be lower than in the others angles for a fixed air velocity. The study led also to a new correlation for the flooding.     

An experimental study on evaporative heat transfer coefficient and applications for passive cooling of AP600 steel containment

After TMI and Chernobyl accidents, many efforts have been made to enhance the nuclear safety with passive features. Among such passive features, the passive containment cooling system (PCCS) has been suggested by Westinghouse in the AP600 plant. The containment with PCCS is a dual containment, and consists of a stainless steel vessel and a concrete wall. In the gap between these structures, air and water can counter-currently pass and cool the steel surface. This paper experimentally investigates evaporative heat and mass transfer at the surface of a falling water film with counter-current air flow in a vertical duct with one-side heated plate. Experiments included various conditions of mass flow rate of film and air. Experimental results show the strong effects of water temperature and air mass flow rate, but little effect of the water flow rate. Also, simple analyses based on heat and mass transfer analogy were performed to evaluate the experimental results. With experimental data, a new correlation on evaporative mass transfer coefficient was developed, and with the correlation, the containment pressure and temperature was calculated for the design basis accident of AP600 by the use of CONTEMPT4/MOD5 code implementation.     

Combinated Flow Pattern Map for Cocurrent and Countercurrent Air-Water Flows in Vertical Tube

Flow patterns for cocurrent and countercurrent air-water flows in vertical tubes (40 and 80mm I.D.) at volumetric flux densities of air and water in the ranges ?115–158 and ?100–102 cm/s were observed. A flow pattern map presenting the entire data of the observed flow patterns, i.e. bubbly, slug and annular flow for each mode of flow operation (upflow, countercurrent flow and downflow) were presented on the j_l vs. j_g plane. The flow pattern maps showed significant difference of flow pattern transition boundaries with upflow, countercurrent flow and downflow. Flow pattern transition curves were smoothly continuous with the change of the direction of water flow, on the other hand the change of flow direction of air showed complicated effect on flow pattern transition near zero j_g . Comparison of the present flow pattern data with the reported general flow pattern maps for upflow showed that the correlation of Taitel et al. for bubble-slug flow transition is applicable to both cocurrent and countercurrent air-water flows.     

Two-phase natural circulation flow of air and water in a reactor cavity model under an external vessel cooling during a severe accident

As a part of a study on a two-phase natural circulation flow between the outer reactor vessel and the insulation material in the reactor cavity under an external reactor vessel cooling of the Advanced Power Reactor (APR) 1400, a Hydraulic Evaluation of Reactor cooling Mechanism by External Self-induced flow-HALF scale (HERMES-HALF) experiment has been performed by using the non-heating method of an air injection. This large-scale experiment uses a half-height and half-sector model of the APR1400. This experiment has been analyzed to verify and evaluate the experimental results by using the RELAP5/MOD3 computer code. The RELAP5/MOD3 results have shown that the water circulation mass flow rate is very similar to the experimental results of the HERMES-HALF, in general. Increases in the water inlet area and the water level in the reactor cavity lead to an increase in the water circulation mass flow rate. The effects of an air injection mass flow rate and the water outlet area on the water circulation mass flow rate are dependent on the water inlet area size. As the water outlet moves to a lower position, the water circulation mass flow rate increases slowly.     

Experimental investigation of the two-phase flow distribution in the outlets of a horizontal multi-branch header

An experimental investigation was conducted to study the two-phase flow distribution in a horizontal header with two inlet turrets and 30 (six banks of five) outlet branches. Tests were performed using air–water mixtures at room temperature and a nominal header pressure of 170.3 kPa. The test matrix included one- and two-turret injection, two inlet water flow rates and four different air flow rates for each water flow rate, giving four different inlet qualities. The outlet flow rates of air and water were measured in all the branches under the condition of equal pressure drop across all branches. The data show that there is significant variation in air and water flow rates among the branches, both in the axial and circumferential directions. The flow distribution among the branches was found to be strongly dependent on the inlet flow rates of air and water, and the type of injection (one or two turrets).     

三氧化铀中微量氟、氯、溴的测定

为了准确测定三氧化铀中氟、氯、溴的含量,建立了用高温水解法处理样品、离子选择电极法同时测定三氧化铀中F-,Cl-,Br-的方法.对影响高温水解反应的因素:水解温度、水解时间、水浴温度、空气流量、馏分体积等进行了条件实验.结果表明,用本法分析三氧化铀中的F-,Cl-,Br-的相对标准偏差均优于10%,F-,Cl-,Br-的重加回收率分别为85%～100%,90%～100%,45%～55%.     

Estimation of fuel and clad temperature of a research reactor during dry period of de-fuelling operation

Heat transfer and fluid flow studies related to spent fuel bundle of a research reactor in fuelling machine has been carried out. When the fuel is in reactor core, the heat generated in the fuel bundle is removed by heavy water under normal reactor operation. However, during the de-fuelling operation, the fuel bundle is exposed to air for some period called dry period. During this period, the decay heat from fuel bundle has to be removed by air flow. This flow of air is induced by natural convection only. In this period, the temperatures of fuel and clad rise. If clad temperature rises beyond a certain limit, structural failure may occur. This failure can result into release of fission products from fuel rod. Hence the temperature of clad has to be within specified limit under all conditions. The objective of this study is to estimate the clad temperature rise during the dry period.In the CFD simulation, the turbulent natural convection flow over fuel and radiation heat transfer are accounted. Standard k-? model for turbulence, Boussinesq approximation for computing the natural convection flow and IMMERSOL model for radiation are used.The steady state and transient CFD simulation of flow and heat is performed, using the CFD code PHOENICS. The steady state analysis provides the maximum temperature the clad will attain if fuel bundle is left exposed to air for sufficiently long time. For safe operation, the clad temperature should be limited to a specified value. From steady state CFD analysis, it is found that steady state clad temperature for various decay powers is higher than the limiting value. Hence transient analysis is also performed. In the transient analysis, the variation of clad temperature with time is predicted for various decay powers. Safe dry time, i.e. the time required for clad to reach the limiting value, is predicted for various decay powers. Determination of safe dry time helps in deciding the time available to the operator to drop the bundle in light water pool for storage. The analysis is found useful in optimizing the de-fuelling process.     

Flooding in a thin rectangular slit geometry representative of ATR fuel assembly side-plate flow channels

Air-water counter-current flow limit experiments were conducted in thin rectangular channels at atmospheric pressure. The parameters were: narrow channel width, either 1.1 mm or 2.2 mm; inlet water temperature, ranging from 294 K to 330 K; channel surface condition, either clean aluminum, aluminum oxide, or acrylic; location and geometry of the air inlet; method of forcing air through the channel; and liquid head above the channel. Experimental results for each set of parameters can be linearly correlated using the square root of the non-dimensional superficial velocities. Channel surface wetting and location and geometry of the air injection had the greatest effect. Narrow channel width, water temperature, method used to force air through the channel, and liquid head above the channel had little effect on the flooding characteristics.     

竖直管内淹没及流向反转的实验研究

本文对竖直管中气体由下向上流动,液体由上向下流动过程的淹没及流向反转问题进行了实验研究。给出了计算淹没及流向反转的关系式。通过实验发现,在一定的液体流量下,增加气体流量与减少气体流量时淹没点有所差别;管壁的干燥条件对流向反转有很大影响。