岭澳核电站1号发电机定子铁芯划伤事件的处理和分析

对岭澳核电站1号发电机在L101大修中发生的定子铁芯划伤事件的后果进行了分析,对处理效果进行了分析和评价,并对铁芯缺陷探测试验在岭澳核电站发电机上的有效性进行了讨论。     

压水堆控制棒位置故障诊断技术及其软件实现

秦山第二核电厂棒位系统使用PLC软件对控制棒位置进行实时监视,对异常现象进行及时判别,大大提高了控制棒位置故障诊断的及时性、准确性。实现了对棒位故障的判别、记录,实现了测量通道性能判定的自动化。对该软件的功能及其使用效果进行了介绍。     

用于磁流体发电的超高温反应堆堆芯设计

本文对磁流体反应堆的堆芯方案进行了探索,对石墨基体燃料和金属陶瓷燃料进行了比较,选择了金属陶瓷燃料进行磁流体反应堆的设计,给出了堆芯方案及堆芯物理、热工计算结果,并对发射掉落事故进行了计算和分析。计算结果可满足设计要求。     

煤田岩性密度测井仪器的研制

本文对岩性密度测井原理、仪器的研制方案等进行了论述。介绍了煤田岩性密度测井仪的主要电路框图,对仪器的刻度进行了探索,并介绍了仪器的性能指标,对测井资料应用提出了展望。     

发电机定子冷却水泵可靠性数据处理及分析

基于实际的现场故障数据,对核电站发电机定子冷却水泵进行了可靠性分析.采用统计数学方法对数据进行了经验分析、指数分布与威布尔分布的拟合,并对拟合结果进行了验证.根据分析结果,提出了设备维修管理建议.     

γ探头刻度辐射场光子注量测量

设计了带铅屏蔽和能对空间各场点进行定点测量的照射盒.成功地解决了空间各场点定点测量的问题,克服了以前场点测量数据分散性较大的缺陷,并对探测器的屏蔽效应修正进行了实验验证.在此基础上对物理测试探测器刻度用场点的光子注量进行了实验测定,给出了刻度场点的光子注量.     

核安全级数字化仪控系统软件验证和确认技术标准研究

文章对VV验证与确认方法进行了总结,并对IEC和IEEE相关标准以及IAEA和NRC的相关法规导则以及我国对应的标准和法规进行了调研分析和总结,重点对IEEE 1012-2012进行了剖析,并对IEEE 1012的历届版本进行了时比分析,对如何应用国际国外VV相关标准提出了建议。最后,在本文总结了VV的关键思想,并为建立我国完善的核电厂核安全级仪控系统及软件VV相关标准体系提出了建议。     

高气压监控漂移管幅度性能的实验研究

对高气压监控漂移管在不同气压下工作性能进行了研究。对测得的气体增益和高压关系与有关理论公式进行了比较;对输出脉冲信号与粒子径迹到阳极丝距离的依赖关系进行了研究,并用带电粒子在漂移管内所产生径迹的原初电离电子漂移过程中的聚集效应进行分析。     

两套HPGeγ谱仪对土壤样品的测量结果比对分析

以比对的手法介绍了两套高纯锗γ谱仪的性能。采用相对测量法．分别用两套谱仪对三个土壤样品进行测量,并进行了自吸收校正,对测量结果进行了分析讨论。     

DF-VI快中子临界装置2号堆芯临界实验

DF-VI快中子临界装置在改造完成、堆芯发生了变化以后，进行了重新启动和一系列的实验测量。测量内容有：根据29次临界实验的数据对2号堆芯平均临界元件数和临界质量进行了计算；应用周期法和棒补偿法对控制棒价值进行了刻度；用逆动态反应性计对安全棒和安全块的价值进行了测量；对单根边缘元件价值和径向元件价值分布进行子测量。通过以上实验测量，确定了DF-VI快中子临界装置2号堆芯的主要安全运行参数。     

Criteria for Optimizing Technical Solutions for NPP

Atomic Energy - Criteria for optimizing technical solutions in designing and modernizing NPP are considered. Based on their analysis, it is shown that it is economically efficient to increase the...     

Need for and requirements for a neutron irradiation facility for fusion materials testing

The construction and operation of an intense 14-MeV neutron source is essential for the development and eventual qualification of structural materials for a fusion reactor demonstration plant (DEMO). Because of the time required for materials development and the scale-up of materials to commercial production, a decision to build a neutron source should precede engineering design activities for a DEMO by at least 20 years. The characteristic features of 14-MeV neutron damage are summarized including effects related to cascade structure, transmutation production, and dose rate. The importance of a 14-MeV neutron source for addressing fundamental radiation damage issues, alloy development activities, and the development of an engineering database is discussed. For these considerations, the basic requirements and machine parameters are derived.     

地震工况下设备土建载荷的计算方法

在设备抗震分析中,设备对基础的作用力是土建设计时所需的重要参数。本文根据不同的工程实例,给出2种设备在地震工况下土建载荷的计算方法,即简便方法和谱分析计算中的刚性区域法,并给出了算例。     

Experimental Results for an Acoustic Driver for MTF

General Fusion is planning to form an FRC or spheromak of 10¹⁷ cm⁻³, 100 eV, 40 cm diameter by merging two spheromaks with reverse or co-helicity. This target will be further compressed in a 3 m diameter tank filled with liquid PbLi with the plasma in the center. The tank is surrounded with pneumatically powered impact pistons that will send a convergent shock wave in the liquid to compress the plasma to 10²⁰ cm⁻³, 10 keV, 4 cm diameter for 7 μs. General Fusion has built a 500 kJ, 80 μs, 6 GW pneumatic impact piston capable of developing 2 GPa (300 kpsi). In this paper we will present the performances achieved to date.     

Principles for Finding Matrices for Immobilizing High-Level Wastes

The principles for selecting matrices for immobilizing high-level wastes are examined. It is concluded that actinides should be separated and embeeded in the matrix separately from fission products. The minimum significant specific activity, regulated by NRB-99, cannot be used to estimate the storage time. It is suggested that such values be established as a function of the leach rate of radionuclides and matrix materials from matrices. For this, a standard leaching method using pulverized materials must be specified. Two criteria are proposed for comparing matrix materials.     

Software for gamma cameras for mapping radioactive contamination

The software for portable systems for obtaining γ image with coding apertures (masks) is described. The software developed controls all systems that form an image and obtain shadow patterns, reconstructs the initial γ-image, and processes previously obtained images. The software is used with portable systems in which URA and MURA type masks with different rank are used as the coding aperture. Programs for modeling the process of obtaining shadow patterns using real apparatus which has different positionsensitive detectors are described. Possible configurations of new apparatus which could be of practical interest are examined.     

Basis for developing samarium AMS for fuel cycle analysis

Modeling of nuclear reactor fuel burnup indicates that the production of samarium isotopes can vary significantly with reactor type and fuel cycle. The isotopic concentrations of ¹⁴⁶Sm, ¹⁴⁹Sm, and ¹⁵¹Sm are potential signatures of fuel reprocessing, if analytical techniques can overcome the inherent challenges of lanthanide chemistry, isobaric interferences, and mass/charge interferences. We review the current limitations in measurement of the target samarium isotopes and describe potential approaches for developing Sm-AMS. AMS sample form and preparation chemistry will be discussed as well as possible spectrometer operating conditions.     

AC—600非能动安全特性分析

AC-600概念设计的研究重点包括堆芯、非能动安全系统及简化系统。本文讨论 AC-600自然循环能力、LOCA 或全厂断电期间,非能动安全系统的性能,也初步讨论了 AC-600对过剩反应性及热工水力瞬态的非能动限制。