基于Halcon的堆芯探测器组件图像定位技术研究

华龙一号（HPR1000）反应堆堆芯探测器组件在使用寿命到期后需要全部拆除更换。由于探测器组件自身偏差较大等因素,不能直接使用安装时的理论坐标作为探测器组件拆除时的定位坐标。本文基于机器视觉软件Halcon开发了一种用于堆芯探测器组件图像定位的算法,该算法使用模板匹配的原理在摄像机捕获的探测器组件图像中进行查找,获取探测器组件的精确坐标。实验证明,该算法具有较高的定位精度,能够满足探测器组件拆除工作对图像定位算法的使用要求。      

基于机器视觉的探测器组件定位技术研究

针对"华龙一号"反应堆堆芯探测器组件水下远距离拆除需求,利用机器视觉技术的快速性和便利性,通过图像识别和处理,实现探测器组件目标位置的快速定位。定位算法充分考虑实际拆除环境中视觉摄像头偏斜、探测器组件倾斜、水雾环境等工况,分别研究算法对相机倾斜、目标倾斜及去除水雾等的适用性。环境试验表明,该算法可快速、准确定位且具有良好的环境适应性,为探测器组件水下顺利拆除提供有力保证。     

反应堆堆芯中子-温度测量探测器研制改进及试验验证

反应堆堆芯中子-温度测量探测器组件是集成了铑自给能中子探测器与热电偶温度计的一体化探测器。该组件可同时测量堆芯中子注量率和燃料组件出口温度。本文重点介绍了堆芯中子-温度测量探测器组件研制过程中的设计方案,针对假想事故条件下可能出现的短路风险,提出优化结构和加工工艺的改进方案,并通过试验验证了方案的有效性,无限振动试验、拉力、热老化和辐照老化等试验结果表明探测器电气连续性能正常,绝缘电阻大于1 GΩ。设计和工艺改进方案满足探测器技术规格书的要求。      

堆芯核测系统通量探测器运动控制的特点

介绍了反应堆堆芯核测系统通量探测器运动控制的特点，并着重介绍了探测器的位置编码、译码电路为消除两级编码器之间齿轮啮合间隙所采取的措施。介绍了送计算机采样同步信号的形成和利用燃料组件定位格架的位置来调整探测器在堆芯中轴向测量区域的方法。最后分析了影响定位精度的因素，为系统检修、改进和设备国产化提供帮助。     

基于辐射探测器阵列的单个γ源定位方法

采用探测器阵列并通过数据的自动处理实现辐射源的定位,是信息时代物联网工程对辐射信息监控的基本要求。为此,本文初步讨论了数学分析法、数学统计法和邻近探测器数据比较法三种定位方法,并采用MCNP5软件对通道内单个γ源的一维定位监控进行了数值仿真分析。结果表明,数学分析法和数学统计法的定位能力均优于工程上常用的邻近探测器数据比较法,前者需要的探测器数量少,但在多个探测器存在时误差随探测器组合而产生较大的变化。数学统计法需要多个探测器形成阵列,但定位精度很高,可用于大剂量或重要放射性部件的精确位置监控。     

乏燃料组件非破坏性测量的叉形探测器

采用总γ和无源中子测量方法建立了叉形探测器。叉形探测器可用于后处理和贮存工厂中ＰＷＲ和ＢＷＲ型的乏燃料组件的燃耗、冷却时间、总钚和总裂变物质含量的测定。     

分布式三测角定位系统的数据融合

本文对集中式多探测器定位同一目标的数据融合进行了一般性的论述，进而对分布式三测角定位系统推导了一个数据融合方法，这种方法改变系统的硬件配置不可以大大提高系统的定位精度。     

一种前放分离式中子测量系统设计与测试

设计了一种前置放大器与探测器分离的中子测量系统,该测量系统将耐辐照性较差的电子学电路与探测器组件分离,通过同轴电缆远距离连接。测试结果显示,该中子测量系统相对固有误差≤8.6%,对Am-Be源与²⁵²Cf源相对响应之差为9%,性能满足设计要求。     

CZT探测器测量核燃料组件铀丰度实验研究

采用CZT探测器、数字谱仪、准直器等组成了1套便携式CZT探测器铀丰度测量装置。该装置可对燃料组件铀丰度进行测定,以便确定相应铀产品丰度符合规定要求。实验研究中,对几类燃料组件丰度进了测量,建立了CZT探测器测量燃料组件铀丰度的方法。现场测量结果表明,铀丰度测量结果相对偏差小于3%,方法简单可靠,装置简便,能满足核材料保障监督和核设施现场测量中的需求。     

2 核电站乏燃料组件燃耗测量系统的改进和大亚湾乏燃料组件燃耗测量

本工作对叉形探测器乏燃料测量系统进行了改进。改进的乏燃料组件测量系统仍包容了总γ、高分辨γ和无源中子3种测量方法。系统的改进涉及以下4个方面。     

Power peak factor for protection systems – Experimental data for developing a correlation

This paper aims to construct a data set that can be used to train neural networks to furnish the power density peak factor during reactor operation. The inputs considered were those available in the reactor protection systems, namely, the axial and quadrant power differences obtained from measured ex-core detector signals, and the position of control rods. The response of ex-core detector signals was measured in experiments performed in the IPEN/MB-01 zero-power reactor. Several reactor states with different power density distribution were obtained by positioning the control rods in different configurations. The power distribution and its peak factor were calculated for each of these reactor states. The obtained results show that the power peak factor correlates well with the control rod position and the quadrant power difference, and with a lesser degree with the axial power differences. The data presented an inherent organisation and could be classified into different classes of power peak factor behaviour as a function of position of control rods, axial power difference and quadrant power difference. The analysis of the data set indicates that the power peak factor can be determined through a neural network having as input the position of control rods. Regarding only signals of ex-core detectors, the data indicate that a neural network may estimate better the power peak factor if the input vector comprises both the axial and the quadrant power differences.     

ADORE: Alternative detector layout optimization for ROP system of CANDU reactors

In CANDU^® reactor design, the regional overpower protection (ROP) systems protect the reactor against overpower in the fuel which could reduce the safety margin-to-dryout. Specifically for the CANDU^® 600 MW (CANDU 6) design, there are two ROP systems in the core, one for each fast-acting shutdown systems. Each ROP system includes a number of fast-responding, self-powered flux detectors suitably distributed throughout the core within vertical and horizontal assemblies. The placement of these ROP detectors is a challenging discrete optimization problem. The DLO (detector layout optimization) module of ROVER-F code was used to design the existing ROP detector layout of CANDU 6 reactors. In the past couple of years, a new methodology for designing the detector layout for the ROP system, called DETPLASA algorithm, has been developed. This method utilizes the simulated annealing (SA) technique to optimize the placement of the detectors in the core. This algorithm was developed to overcome the shortcoming of DLO method to produce a detector layout configuration when the size of the problem is large. An alternative method has been recently developed for solving the ROP detector placement problem. This method is called ADORE (Alternative Detector layout Optimization for REgional overpower protection system). Although technically any stochastic optimization technique can be utilized, presently this method utilizes the SA technique as its optimization engine. This paper presents an overview of ADORE methodology and provides some numerical results from its execution.     

The importance of uncertainties in the ROP detector layout design process for CANDU reactors

In CANDU® reactor design, the regional overpower protection (ROP) systems protect the reactor against overpower in the fuel which could reduce the safety margin-to-dryout. The increase in fuel power could be caused by a localized power peaking within the core (for example, as a result of a certain reactivity device configuration) or a general increase in the core power level during a slow-loss-of-regulation (SLOR) event. This overpower could lead to fuel sheath dryout. In the CANDU® 600 MW (CANDU 6) design, there are two ROP systems in the core, one for each fast-acting shutdown system. Each ROP system includes a number of fast-responding, self-powered flux detectors suitably distributed throughout the core within vertical and horizontal assemblies. A new methodology for designing the detector layout for the ROP system, called the DETPLASA algorithm, has been developed recently. This method utilizes the simulated annealing (SA) technique to optimize the placement of the detectors in the core. The evaluation of the trip setpoint (TSP) corresponding to each detector layout configuration (i.e., each history in the SA algorithm) is performed probabilistically using the ROVER-F code. In this evaluation, there are uncertainties related to both the detector components (i.e., related to the margin-to-trip) and to the fuel channel components (i.e., related to the margin-to-dryout). In this paper, the importance of these uncertainties on the outcome of the detector layout optimization process is evaluated. Some parametric studies have been performed to quantify the effect of uncertainties on the resulting detector layout. Two types of investigations have been performed. First, a given detector layout will be used to explicitly determine the effect of changing the uncertainty values. In this study, 343 sets of uncertainty values are used to produce the corresponding TSP values. The variation in the TSP values is analyzed. Second, three sets of uncertainty values (a subset of uncertainties from the first study) are used in independent DETPLASA executions. The resulting detector layout configurations will be examined to observe the effect of these uncertainties on the final design. Results from these investigations are presented in this paper.     

铠装铂电阻液位测量传感器研究

压力容器内的水位是反应堆运行中的重要参数．基于发热体在液相和汽相介质中放热系数的显著差异．本文提出了一种由铠装铂电阻组成的液位测量传感器,并给出了理论分析结果和0．1～3．0MPa压力范围内的试验结果。结果表明,该传感器原理正确．结构可行．性能可靠。     

New mechanical samples positioning system for irradiations on a radial channel at nuclear research reactor in a full-power continuous operation

This paper describes a new mechanical samples positioning system that allows the safe placement and removal of biological samples for prolonged irradiation, in a nuclear reactor during full-power continuous operation. Also presented herein the materials of construction and operating principles. Additionally, this sample positioning system is compared with an existing pneumatic and automated transfer system, already available at the research reactors.The system consists of a mechanical arm with a claw, which can deliver the samples for irradiations without reactor shutdown. It was installed in the IEA-R1 research reactor at Instituto de Pesquisas Energéticas e Nucleares (IPEN), Sao Paulo, Brazil, and for the past 5 years, the system has successfully operated and allowed the conducting of important experiments. As a result of its introduction, the facility has been in a position to positively respond to the increased demand in studies of biology, medicine, physics, engineering, detector/dosimeter calibrations, etc.It is one example of the appropriated technologies that save energy and resources.     

电荷除法型位置灵敏探测器

本文对电荷除法型位置灵敏探测器的特征和结构进行了描述。并给出了初步的实验结果。     

基于γ测量的球床式高温气冷堆内乏燃料球探测方案的模拟分析

在球床式高温气冷堆中,对排出堆芯的乏燃料球的探测和数量统计是燃料监测的重要内容。按国际原子能机构针对球床式高温气冷堆核安保的要求,对于燃料装卸系统管道内的燃料监测应开发一种独立于现有涡流检测原理的新监测方案。本文提出了一种基于γ测量原理的新探测方案,设计了探测器构型,对其在堆稳态运行时的探测功能进行验证。结合球床式高温气冷堆HTR-10的燃料球放射性核素数据,及对不同球速不同燃耗的燃料球经过探测区域过程的蒙特卡罗模拟分析,验证了此方案对单个燃料球鉴别和计数的可靠性,同时证明了该方案对于燃料球球流探测的可行性,为今后该探测方案的完善和实际装置的制作提供了设计基础。     

Automation of nuclear reactor controls

Two types of monitoring systems suitable for automatic nuclear reactor control are discussed. In the first system, the detector monitors some given point, such as a preset constant neutron flux. This system is suitable for combining the functions of the period meter and indicator, the power level and criticality of the reactor indicators, and for reactor safety control.In the second system, the reactor power follows detector displacement. Such a system can combine the automatic control functions for criticality, period, and power level of the reactor.If a scheme incorporating monitoring systems of both types is devised, then two variations of complex automation of reactor control may be developed. The first variation is easier to adapt to existing installations. The second variation is more sophisticated, and is suitable, probably, for new installations.The advantages of the proposed schemes are that they consist of simple standard elements, that they make possible servo control, and that they ensure constant operating conditions for the detector and apparatus.