中国实验快堆设计中的自主创新

通过对已经完成的中国实验快堆(CEFR)施工设计进行总结和提炼,全面概述了CEFR设计中体现自主创新的思想、方法、经验和成果,客观评价了作为我国第一座快堆的技术艰难性和创新性,并积极分析了所取得的自主创新成果的意义以及对我国快堆事业长期发展的重要性。     

采用虚拟场景技术的高温气冷堆仿真系统研究

仿真系统对10 MW高温气冷堆的堆芯、主回路系统和蒸汽发生器等部件进行分析计算,模拟稳态和瞬态过程。采用虚拟场景技术,按高温气冷堆的实际结构建立三维虚拟场景,用户可在虚拟场景中漫游观测,实时查看仿真计算状态;同时可对仿真数据结果进行分析并以二维、三维图形显示。该仿真系统不仅对高温气冷堆的工程设计、安全分析和人员培训有重要作用,且可以对HTR-10主控室的操作人员进行现场支持及各项研究提供帮助。     

Challenges in spent nuclear fuel final disposal： conceptual design models

The disposal of spent nuclear fuel is a long-standing issue in nuclear technology. Mainly, UO2 and metallic U are used as a fuel in nuclear reactors. Spent nuclear fuel contains fission products and transuranium elements, which would remain radioactive for 104 to 108 years. In this brief communication, essential concepts and engineering elements related to high-level nuclear waste disposal are described. Conceptual design models are described and discussed considering the long-time scale activity of spent nuclear fuel or high level waste. Notions of physical and chemical barriers to contain nuclear waste are highlightened. Concerns regarding integrity, self-irradiation induced decomposition and thermal effects of decay heat on the spent nuclear fuel are also discussed. The question of retrievability of spent nuclear fuel after disposal is considered.     

秦山核电厂运行15年的核安全审评和监督

秦山核电厂是我国自主建造的第一座核电厂,它对我国核电事业的发展有着重要的作用。本文总结了秦山核电厂15年的核安全审评和监督情况,对我国核安全监管工作的开展进行了简单的回顾,对今后我国核安全监管工作的发展提出了建设性意见。     

Steady thermal hydraulic analysis for a molten salt reactor

The Molten Salt Reactor (MSR) can meet the demand of transmutation and breeding. In this study, theoretical calculation of steady thermal hydraulic characteristics of a graphite-moderated channel type MSR is conducted. The DRAGON code is adopted to calculate the axial and radial power factor firstly. The flow and heat transfer model in the fuel salt and graphite are developed on basis of the fundamental mass, momentum and energy equations. The results show the detailed flow distribution in the core, and the temperature profiles of the fuel salt, inner and outer wall in the nine typical elements along the axial flow direction are also obtained.     

求解点堆动态方程的IGear方法

求解点堆中子动力学方程的改进的Gear方法——IGear,以其高阶和大稳定域的性质保持了Gear方法适应性强,计算精度较高的优点,并改进了它的缺点。因此能够灵活应用于各种反应性的输入。计算结果表明:从计算时间和计算精度上看,该方法都可以满足实际工程的需要,是求解点堆动态方程的一种较好的方法。     

核电厂操纵员健康状况的审查

身体健康是核电厂操纵员应具备的资质之一,也是其获得并持有国家核安全局颁发的核电厂操纵员或高级操纵员执照的基本条件。本文依据核安全法规对操纵员健康状况所提出的要求,结合最近几年发布的法律法规,特别是相关国家标准,阐述了对健康状况的审查思路、重要内容和相关准则。     

浅析核电厂规划限制区的设置和监管

根据我国现行法律法规及有关规定,从安全管理（应急准备和预防外部人为事件）和经济发展的角度,分析了核电厂规划限制区的划分和设置,指出核电厂规划限制区监管的现状和不足,提出了完善法律法规建设、设立核电厂规划限制区发展基金以便动态管理和补偿等建议。     

Finding an optimization of the plate element of Egyptian research reactor using genetic algorithm

The second Egyptian research reactor ET-RR-2 went critical on the 27th of November 1997. The National Center of Nuclear Safety and Radiation Control （NCNSRC） has the responsibility of the evaluation and assessment of the safety of this reactor. The purpose of this paper is to present an approach to optimization of the fuel element plate. For an efficient search through the solution space we use a multi objective genetic algorithm which allows us to identify a set of Pareto optimal solutions providing the decision maker with the complete spectrum of optimal solutions with respect to the various targets. The aim of this paper is to propose a new approach for optimizing the fuel element plate in the reactor. The fuel element plate is designed with a view to improve reliability and lifetime and it is one of the most important elements during the shut down. In this present paper, we present a conceptual design approach for fuel element plate, in conjunction with a genetic algorithm to obtain a fuel plate that maximizes a fitness value to optimize the safety design of the fuel plate.