研究性重水反应堆HWRR UO_2堆芯的物理启动

对HWRR的UO_2堆芯进行了物理启动。在实验进程中成功地在线应用了计算机。实验结果较好地验证了理论设计,也为运行和用户提供了必要的物理性能数据。对所测得的控制棒栅反应性曲线的适用性作了论证和说明。为运行中剩余反应性的度量提供了简便实用的方法。     

研究性重水反应堆(HWRR-3)最大允许功率的确定和监测

反应堆运行功率是一个重要的监测参数。本文扼要地叙述了HWRR-3最大允许功率的确定和监测。描述了计算方法,给出了计算结果和误差分析。该工作使重水反应堆实现了在线计算和实时监测,它使反应堆得到了实时的、可靠的监督,方便了运行人员,增加了运行的安全性。     

γ刻度室的散射测量

本文介绍了铅准直器 γ 刻度室的散射实验研究。用几种方法测量了不同使用距离上的相对散射系数,其结果小于5%。测量了 γ 散射能量,并探讨了准直器的散射,从而了解了辐射场的性质。文中还提出了值得注意的几个问题。     

重水质谱分析

对高浓度重水进行了质谱分析,利用同位素交换平衡法制备了氘样品。根据实验工作的要求,部分地改进了МИ1301型质谱计。拟定了分析方法。对导致产生误差的各种因素进行了分析,引入了必要的校正值。给出高浓度(>99%)重水氘的百分浓度数据的准确度为±0.02%。     

一种压电式声探头的研究

本文研究了一种压电式声探头。介绍了声探头的结构,分析了声能在探头内的传送,计算了声探头的固有频率。研究了一种改善声探头信噪比的措施,介绍了应用互相关技术提高探测系统抗干扰能力的方法,给出了钠空穴噪声的测量结果。这种探头主要应用于探测钠空穴噪声,亦可用于探测沸腾噪声及钠-水反应的声噪声。     

原则和依据:核科学领域量和单位的国家标准

综述了制订核科学领域量和单位两项国标的原则和依据。引进了物理量名称新的构词法和定名导则。对某些重要物理量的概念作了说明。澄清了一些错误用法。从与国际标准、国际辐射单位与测量委员会推荐的量相比较中阐明了该标准的特点,为其在全国深入贯彻实施提供了有用资料。     

硝酸体系中锕的三烷基氧膦萃取

本文研究了TRPO-煤油对硝酸体系中的锕的萃取,确定了萃取络合物的组成;测定了表观平衡常数;并研究了各种因素对Ac的萃取的影响。在实验基础上推导出了计算Ac的分配比的经验公式。还研究了TRPO-煤油对常量La的萃取,并讨论了使用TRPO萃取实现La,Ac分离的可能性。     

原则和依据:核科学领域量和单位的国家标准

综述了制订核科学领域量和单位两项国标的原则和依据。引进了物理量名称新的构词法和定名导则。对某些重要物理量的概念作了说明。澄清了一些错误用法。从与国际标准、国际辐射单位与测量委员会推荐的量相比较中阐明了该标准的特点,为其在全国深入贯彻实施提供了有用资料。     

压水堆核电站优化堆芯燃料管理方法

本文介绍了压水堆核电站优化堆芯燃料管理的计算机模拟。讨论了优化准则,目标函数和优化算法。在计算中还考虑了各种核截面的空间燃耗效应。编制了2D-FEOF程序,用FORTRAN-77语言写成,在IBM-4341机上对压水堆的一个例题进行了计算,得到了预期的效果。     

辐射损伤诱发CCD敏感参数退化分析

研究了CCD敏感参数受辐照后的退化情况。分析了电荷转移效率受不同粒子辐照后的退化情况,并列表进行了对比;分析了暗电流受辐射增大的规律;分析了平带电压和阈值电压受辐射后的漂移现象。初步确定了CCD敏感参数的辐射损伤阈值范围。     

油气工业中放射性废物的处理和处置

油气的开采会产生大量的放射性废物,对放射性废物的处理与处置事关公众和环境的辐射安全问题。本文从油气工业放射性废物的源项和存在形式等特征出发,对放射性废物的临时贮存、污染设备的去污及放射性废物的处理、处置过程中涉及的技术方法和相关管理要求进行了介绍,为实践中选择合理可行的处理、处置方案以及建立油气工业放射性废物监管体系提供借鉴和参考。     

Safety functions and component classification for the HTR-10

In the design and construction of the HTR-10, the standards and criteria of design and manufacture for structures, systems and components must be defined. This paper refers to the relative nuclear safety codes to formulate the principles of safety classification and the relative requirements of design and manufacture, according to the safety philosophy and feature of the HTR-10, and the requirements for safety functions of structures, systems and components. We can find practical use and application meaning of this work in the design and manufacture of the HTR-10. It will be used to ensure the safety and reliability of the HTR-10.     

核电站设备可靠性数据库的建立与应用

以大亚湾核电站为例,论述了核电站设备可靠性数据的采集与处理、可靠性参数的分析计算方法及可靠性数据库的建立与应用等。数据源涉及到设备的设计信息、运行信息、维修信息、定期试验记录等。在大亚湾核电站运行经验的基础上,形成了大亚湾核电站设备可靠性数据库,为深入地、客观地记录核电站各类设备的运行历史和现状、监控电站设备,特别是与安全相关设备的状态,提供了有效的工具;为加强设备的可靠性与可用性管理、确保电站的安全经济运行,提供了非常有实用价值的信息;同时还为核电站的安全管理、可靠性分析、概率安全评价、以可靠性为中心的维修及经济性管理等领域里的新技术在核电站的应用研究与开发,提供了必不可少的数据。     

Decommissioning of the TVR Research Heavy-Water Reactor at the Institute of Theoretical and Experimental Physics

The key work on decommissioning of the TVR research heavy-water reactor at the Institute of Theoretical and Experimental Physics is described. The processes involved in the preparation for hauling away the spent nuclear fuel, mothballing the high-activity heavy water, salvaging the contaminated water in the holding pond, and removal of radioactive contaminants from the holding pond are described. Special attention is devoted to selecting a variant of decommissioning of the TVR and solving the problems associated with the implementation of decommissioning. The processes of dismantling the connecting pipes of the horizontal experimental channels inside the reactor vessel and preparing the fittings and equipment for performing this work are described.It is reported that work has been performed on the dismantling of the heavy- and light-water and gas loops of the reactor and on the dismantling of the experimental setups operating on the neutron beams of the horizontal and vertical channels of the reactor.     

对轴流泵前置导轮设计的探讨

对轴流泵前置导轮的设计与配套作了初步研究,主要内容包括：前置导轮设计参数的分析与确定;导轮尺寸的拟定;导轮叶片的计算与导轮的叶片绘形等。所设计的导轮能够有效地减轻轴流泵的水力振动和噪音,可为泵站技术改造提供参考。     

Plan of ITER remote experimentation center

Plan of ITER remote experimentation center (REC) based on the broader approach (BA) activity of the joint program of Japan and Europe (EU) is described. Objectives of REC activity are (1) to identify the functions and solve the technical issues for the construction of the REC for ITER at Rokkasho, (2) to develop the remote experiment system and verify the functions required for the remote experiment by using the Satellite Tokamak (JT-60SA) facilities in order to make the future experiments of ITER and JT-60SA effectively and efficiently implemented, and (3) to test the functions of REC and demonstrate the total system by using JT-60SA and existing other facilities in EU. Preliminary identified items to be developed are (1) Functions of the remote experiment system, such as setting of experiment parameters, shot scheduling, real time data streaming, communication by video-conference between the remote-site and on-site, (2) Effective data transfer system that is capable of fast transfer of the huge amount of data between on-site and off-site and the network connecting the REC system, (3) Storage system that can store/access the huge amount of data, including database management, (4) Data analysis software for the data viewing of the diagnostic data on the storage system, (5) Numerical simulation for preparation and estimation of the shot performance and the analysis of the plasma shot. Detailed specifications of the above items will be discussed and the system will be made in these four years in collaboration with tokamak facilities of JT-60SA and EU tokamak, experts of informatics, activities of plasma simulation and ITER. Finally, the function of REC will be tested and the total system will be demonstrated by the middle of 2017.     

The laboratory investigation of the experimental nuclear reactor VVR-S

Results are given in this paper of the laboratory investigation of the characteristics of the experimental reactor VVR-S undertaken with the aim of studying the neutron and physical parameters which are the most important for putting the reactor into operation and for its exploitation. As the result of the experimental work carried out, the critical mass and the maximum and operating fuel charges were found, the compensating capacity of the control and emergency rods was determined, the influence of the various factors (variation in the temperature of the water in the active zone, variations in the properties of the reflector, etc.) on the reactivity was studied, the distributions of neutron density with height and along the radius of the active zone were measured, and the operating time of the control rods was obtained.In conclusion the authors express their gratitude to T. N. Zubarev for discussion of the results and to O. I. Liubimtsev and I. V. Koptev for help in the work.     

关于我国核电厂退役工作的思考

随着我国核电机组的数量和运行时间的增加，核电厂退役工作越来越重要。如何安全、经济、环保地退役，关系着核工业持续发展，以及生态环境安全和子孙后代的健康。本文从国际核电退役经验反馈和市场发展的角度出发，结合我国核退役规划要求，提出我国未来核电厂退役应开展的重点工作，包括:完善退役相关法规、标准；坚持自主化、企业化、市场化、专业化道路，合作共赢；落实全生命周期对于退役的要求；加快退役关键技术和设备研发；保障退役费用。      

开挖损伤区(EDZ)对核素迁移的影响

随着核电的发展,核电站产生的乏燃料处理处置受到了大众的高度关注.通过对嬗变法、稀释法和隔离法等方法的综合对比,目前,高放废物深地质处置是国内外公认处理核废物的最佳办法.在处置库建造阶段,由于开挖使得围岩中应力重新分布,围岩发生扰动,岩体内部原生裂隙出现扩展、连通,产生新生的微裂隙,岩体的渗透系数变大,这种区域即为开挖损...     

Hastelloy C-276/316L脉冲激光异质焊接微观组织研究

为评价激光焊接AP1000部件工艺的可靠性,探究Hastelloy C-276与316L异质焊接焊缝的元素偏析及组织结构,利用Nd:YAG脉冲激光进行焊接,借助光学显微镜和电子探针X射线微区分析仪等分析测试仪器,对焊缝显微组织、元素成分及金相形貌进行分析。结果表明：焊缝组织晶粒细化,焊缝中部以细小等轴晶为主、边缘以柱状晶为主,且焊接接头两侧热影响区极窄;依据元素宏观分布,焊缝可分为3个区域,焊缝两侧元素成分急剧变化,中部均匀;元素存在微观偏析,晶界处Mo元素富集。焊缝组织以γ奥氏体为主,并未发现明显δ铁素体生成。