辐射防护体系的一些发展概况

讨论了现有辐射防护原则解决实际防护问题中面临的主要问题 ,在此基础上简要地介绍了基于“可控制剂量”概念的防护体系。     

“华龙一号”反应堆堆芯与安全设计研究

“华龙一号”是我国自主设计研发的具有完整知识产权的第三代百万千瓦级压水堆核电技术。本文介绍了“华龙一号”的产生历程，系统论述了“华龙一号”反应堆堆芯与安全设计特点，包括“华龙一号”研发过程中开展的堆芯核设计、热工水力设计、安全设计、设计验证及“华龙一号”持续开展的设计改进与优化等内容，通过采用新的设计理念和设计技术，全面提高了“华龙一号”作为三代核电技术的经济性、灵活性和安全性。      

An Investigation for Ground State Features of Some Structural Fusion Materials

Environmental concerns associated with fossil fuels are creating increased interest in alternative non-fossil energy sources. Nuclear fusion can be one of the most attractive sources of energy from the viewpoint of safety and minimal environmental impact. When considered in all energy systems, the requirements for performance of structural materials in a fusion reactor first wall, blanket or diverter, are arguably more demanding or difficult than for other energy system. The development of fusion materials for the safety of fusion power systems and understanding nuclear properties is important. In this paper, ground state properties for some structural fusion materials as ²⁷Al, ⁵¹V, ⁵²Cr, ⁵⁵Mn, and ⁵⁶Fe are investigated using Skyrme–Hartree–Fock method. The obtained results have been discussed and compared with the available experimental data.     

国内外部分小型压水堆安全特性比较分析

随着核电行业的发展,尤其是福岛事故之后,小型反应堆因具有放射性源项小、结构简化与大型压水堆相比有独特优势的特点,引起了人们的关注。美国、日本、俄罗斯和韩国等相继开发了小型堆技术,我国也相继开发了低温供热堆和高温气冷堆等小型堆技术。目前小型压水堆是各国优先开发的目标。针对世界上众多的小型压水堆技术,我国选取了m Power、Nu Scale、ACP100和NHR-I 4种反应堆技术为代表进行总结并对比其设计特点和设计参数,尤其对四种堆型的安全特性进行比较分析,为后续的堆型发展提供思路。     

对计算机断层扫描技术中几个问题的探讨

本文对计算机断层扫描技术中所选择滤波函数的不同，射线束宽度的差异，探测器的响应、数据的采样及旋转中心的偏移等因素影响图像重建质量分别进行了讨论和分析。实验结果表明，这几个因素对重建后的图像质量产生的影响都是不可忽视的，尤其是在某些情况下，将会导致产生较大的误差。     

海上浮动核电站总体设计初探

通过分析国际上现有堆型的优劣及其在舰船上的应用成果,建议海上浮动核电站采用技术成熟的压水堆,并对反应堆功率与换料周期给出原则性建议。以单点系泊型式的船型浮动核电站为例,根据各舱室的主要功能进行分区,提出舱室划分原则。同时分析了海上浮动核电站主尺度的主要制约因素,阐述了总体性布局原则,并着重介绍了反应堆舱内设置的安全壳、安全围壁、放射性废物管理系统、生物屏蔽设计的基本原则。同时,结合海上浮动核电站的特点,对一些关键系统如二回路、控制室、电力系统、物理防护等的设计原则进行了介绍。      

Study of Dynamic Features of Surface Plasma in High-Power Disk Laser Welding

High-speed photography was used to obtain the dynamic changes in the surface plasma during a high-power disk laser welding process.A color space clustering algorithm to extract the edge information of the surface plasma region was developed in order to improve the accuracy of image processing.With a comparative analysis of the plasma features,i.e.,area and height,and the characteristics of the welded seam,the relationship between the surface plasma and the stability of the laser welding process was characterized,which provides a basic understanding for the real-time monitoring of laser welding.     

超临界压力水循环系统非线性水动力特性研究

建立超临界压力下自然与强制水循环回路的统一水动力模型,结合超临界压力下特殊的物性变化、非线性动量传输与系统耦合特征,采用基于延拓的非线性数值方法,系统比较研究了超临界压力下自然与强制循环水系统的复杂水动力特性,揭示了超临界压力下自然与强制循环系统独特的非单调的流量-加热功率关系及其机制与特点.分析了系统传热特性,并讨论了加热段入口温度、局部阻力对自然和强制循环水动力特性和系统传热的影响规律.     

断电事故对核主泵安全特性影响的试验研究

介绍了国内外反应堆冷却剂泵在发生各种事故情况下的理论及试验研究情况,针对核主泵断电惰转过程中的瞬态水力特性进行了试验研究,对试验结果进行了讨论.介绍了用于断电试验的试验设备及试验方法,着重分析了惰转过程中流量、转速、振动参数,并用四次多项式拟合的方法模拟惰转过程的流量、转速随时间的变化.试验结果表明:在断电瞬间,泵的流量和转速迅速下降,试验结果符合安全标准规定;轴承座位移振动在断电瞬间突然加强,在断电后一段时间转轴振动才发生变化.试验和分析结果有助于认识核主泵发生全厂断电事故时的水力特性,为核主泵的安全评价提供基础依据.     

Future Features

Abstract

The new IAEA regulations TS-R-1 (ST-1 Revised 1996) have been fully in force for all modes of transport since 1 January 2002. Specific requirements in TS-R-1 affect the transport of non-fissile and fissile excepted uranium hexafluoride (UF₆). Under the auspices of the World Nuclear Transport Institute (WNTI), an industry working group has made preparations for the introduction of TS-R-1. The existing containers used have been evaluated against the new requirements. The free drop test needed an improved valve protection and a new valve protection assembly (VPA) has been successfully designed and tested. An H(M) approval has been applied for at the US Department of Transport (US-DOT). This approval was issued in August 2001 and has been validated in other countries in North America and Europe. Russia has also validated the US-DOT approval. Current activities of the WNTI industry working group concentrate on compliance with the thermal test requirement in TS-R-1. This must lead to the availability of an H(U) approval as required after 31 December 2003. This paper describes the certification and validation for the H(M) approval and the work in progress with regard to achieving H(U) approval. The paper specifically focuses on packages for non-fissile and fissile excepted UF₆.     

Future Features

Abstract

BNFL have carried out the marine transport of irradiated nuclear fuel since the 1960s. Since 1976 BNFL have managed the transport system for this business and to date nearly 300 voyages and the transport of over 8000 tonnes of irradiated fuel have been completed. Between 1986 and 1993 the IMO (International Maritime Organization) developed the INF code for ships carrying varying quantities of irradiated fuel, plutonium and high level waste. The PNTL vessels meet the highest level of this code (INF3). This paper described the design and operation of the ships and their cargo. The management of the transport system is also described, including emergency response plans and salvage arrangements.