一种智能化闪烁核子秤通过鉴定

由中国核工业总公司404厂石家庄辐射中心研制的一种高精度的核子秤——SY—5000型智能式闪烁核子秤已在京通过了中华人民共和国计量器具新产品定型鉴定。 由于SY—5000型核子秤采用了线状放射源和高灵敏、高效率的闪烁探测器,首创了新型的自动稳峰技术,因此,其性能指标有了重大突破。 根据中国计量科学研究院的测试检定结果表明,该仪器的动态计量精度为0.15%,远远优于国际法制计量组织所颁发的核子秤技术标准中最高准确度等级所规的技术指标     

ZJH36/127S隔爆兼本质安全型核子秤的设计

简单介绍了ＺＪＨ３６／１２７Ｓ型防爆核子秤的设计依据、设计原则和设计过程，并列举了核子秤应用的两种基本形式。     

激光核子秤的误差分析

激光核子秤是根据专利ZL 02 128861.5所设计的一种新型皮带秤。分析了激光核子秤存在的偶然误差和系统误差,可以作为设计激光核子秤的参考。还把激光核子秤与核子皮带秤、电子皮带秤的主要误差做了简单的比较。     

微机核子秤的误差分析及改进

对影响核子秤的因素进行了理论阐述和试验证明,建立了核子秤误差的表达式,求证存在最佳负荷因子,在外界环境变化时,必须对核子秤的参数进行重新整定,在此基础上设计了新的程序,并将它们应用到某码头的输煤系统中,结果表明,核子秤的计量精度大大提高了。     

WINDOWS下的微机核子秤配料系统软件

本文介绍了在Ｗｉｎｄｏｗｓ下开发的微机核子秤配料系统软件，简要叙述了微机核子秤配料系统的构成，给出了软件的功能结构及实现方法。     

基于LabVIEW的核子秤计量系统

核子秤利用低能γ射线透过物料时被物料吸收衰减的规律来测量物料重量,是一种非接触式的连续计量装置,具有结构简单、运行可靠等优点.LabVIEW作为一种图形化的编程语言,是一种标准的数据采集和仪器控制软件,论文针对核子秤测量原理和特点,利用LabVIEW编程环境设计了一种核子秤计量系统监控软件,软件构架主要由监控软件、数据库和Web服务三大基本模块组成,实现了对核子秤计量数据采集、状态监控、数据管理及远程监控的功能.     

塑料闪烁体核子秤的研制

塑料闪烁体核子秤是一种新型的非接触式在线计量和控制仪表。上有安装维护简单，动态精度高，可靠性好等特点，介绍了塑料闪烁体核子秤的工作原理，结构及性能。     

长棒辐射源配长探测器型核子秤的静态实验研究

根据核子秤的基本原理和计量物料的实际情况，对采用长棒辐射源（下称长棒源）和长电离室可以减小核子秤的辐射源活度这一方面进行了理论分析和静态比较实验。实验结果表明：在下降低计量精度、使用长电离室的情况下，这一方法可以把核子秤的辐射源活度由原来的３．０－３．７ＧＢｑ减小到３７０ＭＢｑ左右。     

核子皮带秤物理模拟实验

用皮带运输物料煤进行的核子皮带秤物理模拟实验测量了核子秤的线性、重复性和长期稳定性。初步研究了煤的堆积形状、偏载、成分含量变化对核子秤计量的影响,为核子皮带秤的安装、调试和运行提供了物理依据。     

防爆核子秤通过技术鉴定

一种不受煤矿井下恶劣环境影响的连续计量装置——防爆型核子秤日前已通过中国统配煤矿总公司技术发展局组织主持的部级技术鉴定。 该防爆型核子秤是由中国矿业大学机械系研制成功的,该系科技人员为此经历了近3年的潜心研究。 防爆核子秤是根据被测物料对γ射线的吸收原理而设计制造的,它可作为一种用于煤矿矿井中专用的计量装置。由于它的防爆性提高了使用时的安全程度,定将受到煤矿工人的欢迎。     

Maintainability versus disposability

Some aspects of the interrelationship of maintainability and disposability are set out together with their application to nuclear power plants. Reference is made to military and industrial fields and long service examples are given from bridge engineering in the absence of total life case histories for nuclear plant.Characteristics of failure, disposal of components and modelling are discussed and factors are given which weigh in favour of either maintainability or disposability.     

同一物理量观测值的处理

在核数据评价和测量中,经常遇到同一物理量观测值的处理。当这些数据在统计学上一致时,很容易用统计方法处理,但存在系统误差时,处理就很困难。本文提出了一个普遍适用的方法。根据这个方法,由给出的系统误差的协方差矩阵,可计算平均值和它的误差。加权平均值、算术平均值、内误差、外误差和算术平均误差只是这个方法的特殊情况。给出的实例表明,这个方法是合理的。     

高体积份额下包覆颗粒弥散燃料等效热学模型

准确预测核燃料的内部温度场分布，对于多层包覆颗粒弥散核燃料元件的设计及筛选具有重要的指导意义。在多层包覆颗粒及其弥散块体的等效热导率模型基础上，本文针对高体积份额情况分析建立了等效传热计算方法及其数值模型，并研究了燃料颗粒的空间分布、颗粒尺寸、团聚等因素对核燃料元件温度场的影响。本研究有助于理解多层包覆颗粒弥散核燃料元件的微观-宏观传热机制，为核燃料的设计、优化和安全分析提供了分析工具。      

A very small LWR installed in the underground in the city

The effective of the nuclear reactor as the source of heat supply is more expected considering that the energy demand will increase and that the energy consumption structure will convert in Japan. The output scale of such reactors is to be less than 300MWt from the limit of supply area. We are studying two types of such reactors. One is the system for district heat supply with a nuclear reactor MR100 type and the other is for heat supply in buildings with a cassette type nuclear reactor MR1. The conception of these nuclear reactors is originated from the marine nuclear reactor technology. They are of highly safety with passively safe system and highly load following ability.     

中国核技术应用产业发展现状

核技术应用作为高技术产业逐渐受到政府重视,并于“十三五”正式被国家纳入加强前瞻布局的战略性新兴产业。为更好地把握核技术应用产业高速发展的战略机遇期,本文在《2016—2017核技术应用学科发展报告》研究的基础上,通过进一步调查研究,总结了我国核技术在工业、医学、农业和社会安全领域应用的整体发展情况,以及2018年以来取得的最新进展,并对上述领域的技术水平、产业规模及发展前景进行了分析。结合核技术应用发展所面临的形势,对比了我国与日韩等国家核技术应用产业的经济规模,展望了我国核技术应用产业的发展前景及趋势。     

Discussion of the paper: “Dynamic decoupling of secondary systems, by A.K. Gupta and J.M. Tembulkar, in: Nucl. Engrg. Des. 18 (1984) 359”

Technical aspects of seismic isolation systems show merit for their use in nuclear power plants. Less quantifiable non-technical aspects must be evaluated in the decision to employ a seismic isolation system.First, non-technical aspects are discussed. An historical and applications perspective is given, and it is suggested that the number of applications of seismic isolation systems is correlated with the amount of research activity in this area. For nuclear plants, it is suggested that application of seismic isolation systems is in part related to standardized plant designs in high seismic regions. Also, for nuclear plants, it is suggested that direct capital cost, enhanced seismic safety, regulatory licensing and unknown locations of nearby active faults are all factors which can weigh in favor and/or not in favor for seismic isolation application.Second, technical aspects are discussed. The technical results show that seismic isolation reduces building response, and reduces floor response spectra/equipment response. These results combine in application to reduce seismic risk and thus enhance safety for nuclear plants.     

聚变-裂变混合堆水冷包层中子物理性能研究

研究直接应用国际热核聚变实验堆（ITER）规模的聚变堆作为中子驱动源，采用天然铀为初装核燃料，并采用现有压水堆核电厂成熟的轻水慢化和冷却技术，设计聚变-裂变混合堆裂变及产氚包层的技术可行性。应用MCNP与Origen2相耦合的程序进行计算分析，研究不同核燃料对包层有效增殖系数、氚增殖比、能量放大系数和外中子源效率等中子物理性能的影响。计算分析结果显示，现有核电厂广泛使用的UO₂核燃料以及下一代裂变堆推荐采用的UC、UN和U₉₀Zr₁₀等高性能陶瓷及合金核燃料作为水冷包层的核燃料，都能满足以产能发电为设计目标的新型聚变 裂变混合堆能量放大倍数的设计要求，但只有UC和U₉₀Zr₁₀燃料同时满足聚变燃料氚的生产与消耗自持的要求。研究结果对进一步研发满足未来核能可持续发展的新型聚变-裂变混合堆技术具有潜在参考价值。     

Dynamic testing of full-scale nuclear power plant structures and equipment

Three steps are required in the design of reliable nuclear power plants to be located in seismic areas. In addition to development of realistic analytical models, it is necessary to perform dynamic tests to verify the models and acquire the information needed to establish the dynamic parameters for modeling. The third and final step is to perform high level proof tests to validate analysis and test results. This report is an overview of dynamic testing methods.Testing can be performed in the laboratory or in the field. Laboratory tests are useful because a wide range of effects can be studied and test parameters are more easily controlled. Care must be exercised to insure that the laboratory situation faithfully reproduces the actual structure in such details as supports, appurtenances, appendages, and mounting methods. In general, laboratory methods permit high level excitation of structures weighing up to a few metric tons (a few facilities in the world have capabilities up to 100 t). Since actual structures of interest to nuclear power plant designers often weigh up to 10 000 t, field testing is also important. Test procedures have been developed, using portable structural vibrators, for testing structures as large as nuclear power plant containment buildings. High level tests can be performed using explosives buried in the soil to excite structures. Recent work performed by the author demonstrates that explosive tests which produce a predetermined, specified response spectrum can be conducted.     

Comparison of thermo-hydraulic performances of large scale vortex flow (LSVF) and small scale vortex flow (SSVF) mixing vanes in 17 × 17 nuclear rod bundle

Spacer grids in the nuclear fuel rod assembly maintain a constant distance between rods, secure flow passage and prevent the damage of the rod bundle from flow-induced vibration. The mixing vanes attached to the spacer grids generate vortex flows in the subchannels and enhance the heat transfer performance of the rod bundle. Various types of mixing vanes have been developed to produce cross flows between subchannels as well as vortex flows in the subchannels.The shapes of the mixing vane have been improved to generate larger turbulence and cross flow mixing. In the present study, two types of large scale vortex flow (LSVF) mixing vanes and two types of small scale vortex flow (SSVF) mixing vanes are examined. SSVF-single is conventional split type and SSVF-couple is split type with different arraying method. LSVF mixing vane has different geometry and arraying method to make large scale vortex. 17 × 17 rod bundle with eight spans of mixing vanes is simulated using the IBM 690 supercomputer. The FLUENT code and IBM supercomputer is employed to calculate the flow field and heat transfer in the subchannels.Turbulence intensities, maximum surface temperatures of the rod bundle, heat transfer coefficients and pressure drops of the four kinds of mixing vanes are compared. LSVF mixing vanes produced higher turbulence intensity and heat transfer coefficient than SSVF mixing vanes. Consequently, LSVF mixing vane increases the thermal efficiency and safety of the rod bundle.