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通过研究设计质量构成、设计过程控制流程、设计产品的寿命周期和转换条件、核动力装置的设计过程,对核动力装置设计质量的形成机理进行了系统分析和薄弱环节的识别,并对设计质量问题产生的原因进行了初步分析,探讨了核动力装置设计过程优化方法,并提出了改进和优化设计方法的措施。 相似文献
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辐射防护最优化是核电厂辐射防护设计中的关键问题之一。本文结合国际原子能机构(IAEA)提出的辐射防护最优化设计策略,围绕核电厂辐射防护最优化设计过程中的设计目标、设计内容与评估、确保持续改进等几个方面对华龙一号核电厂的辐射防护优化设计进行了概述,对华龙一号设计中涉及的辐射源项优化、辐射分区优化、事故后辐射防护设计优化、职业照射剂量评价、环境排放设计优化等方面开展的工作进行了介绍。辐射防护最优化原则在 “华龙一号”(HPR1000)的设计工作中得到了有效的贯彻与执行。 相似文献
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本文总结了脉冲堆燃料元件设计经验,论述了脉冲堆工作特点、燃料性能、燃料元件设计准则和设计内容,对脉冲堆燃料元件设计提出了指导性建议。 相似文献
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施红 《核工程研究与设计》2006,(2):33-38
概要介绍建筑防火性能化设计的发展背景、基本概念和支撑体系、设计步骤等主要内容,分析了性能化设计方法在推行中所遇到的一些困难,提出了对性能化设计未来发展的展望和建议。 相似文献
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文中主要介绍了中国AC-600核电站在设计参数、堆芯设计、主系统、非能动专设安全设施等方面的设计特点,并与美国AP-600核电站设计进行了比较,给出了AC-600与AP-600的主要区别。 相似文献
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AP1000核电厂反应堆冷却剂系统布置设计,在满足系统功能的前提下,充分考虑了屏蔽防护、核级部件在役检查、模块化设计、内部灾害防护等方面的要求。反应堆冷却剂系统主设备及主回路采用了紧凑型的布置方式,改善了环路配置的经济性,波动管布置在考虑足够柔性的基础上采用了大倾斜角连续上坡的方式,降低了波动管在运行过程中出现热分层的可能性,稳压器安全阀及ADS第1、2、3级集中布置在稳压器顶部,组合成一体化的模块Q601,改善了反应堆冷却剂系统布置结构。 相似文献
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Martin Mittwollen Dirk Eilert Martin Kubaschewski Vladimir Madzharov Kuo Tian 《Fusion Engineering and Design》2012,87(5-6):561-564
The International Fusion Material Irradiation Facility (IFMIF) is designed to study and qualify structural and functional materials which shall be used in future fusion nuclear power plants. During the current engineering validation and engineering design activities (EVEDA) phase the development of e.g. an optimized layout and arrangement of the cells (Access Cell, Test Cell, and Test Module Handling Cells) is of major interest.After defining different functions for the individual cells like e.g. large scale/fine scale disassembling of test modules a first layout has been developed. This design followed requirements like having a minimum of carrier changes to avoid sources of failures. On the other hand it has had to be a compact arrangement of cells due to restrictions from plant layout. A row of changes of transfer direction, and different crane systems were the consequence.Constructive discussion with project team results in the statement, that for reasons of being reliable and fast, layout and arrangement of cells goes first, plant layout then will follow.The chance for big improvements was taken and the result was a simplified design with strong reduced number of functional elements, and increased reliability and speed. 相似文献
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浮动核电站是驻泊在海上的核动力电厂,主要辐射源集中在堆舱区域。堆舱内部是包容反应堆及一回路系统等辐射源的船舶舱室,堆舱外包括舷侧和船底两大区域。堆舱内部的辐射分区与陆上核电站相似,而堆舱外区域则需要重新考虑,导致在浮动核电站在辐射分区标准选择方面,堆舱内可参考陆上核电站设计方法,但堆舱外区域则缺乏参考标准。本文给出了浮动核电站辐射分区的总体特征,重点研究了影响浮动核电站堆舱外区域辐射分区的制约因素,给出了堆舱舷侧与底部分区设计的解决方案,兼顾了辐射安全、较高辐射区管理成本和经济成本要求,可供工程人员设计参考。 相似文献
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The paper presents the results of conceptual design of the integral reactor plant of enhanced safety for a small-size floating NPP which is transported to the operation site in the state most prepared for operation and which is designed for power supply to remote and not easily accessible areas. Schematic flow diagrams, design and layout of NSSS and reactor plant as a whole are presented, as well as basic specifications. 相似文献
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简要概述了华能山东石岛湾核电厂高温气冷堆核电站示范工程(简称HTR-PM)的主控室和备用停堆点的整体设计,着重对主控室和备用停堆点的功能设计、台盘布置、主要作用和特点进行了介绍和分析,为以后的实际工程提供参考。 相似文献
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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。 相似文献
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Safety requirements and design considerations are examined for a nuclear hydrogen production system that consists of High Temperature Gas-cooled Reactor (HTGR) and a hydrogen production plant by thermochemical water splitting iodine–sulfur process (IS process). Requirements in order to construct hydrogen production plants under conventional chemical plant regulation are identified in order to take into account a fundamental difference in safety philosophy between the nuclear facility and chemical plant and meet requests from the potential users of nuclear heat. In addition, safety requirements for the collocation of the nuclear facility and hydrogen production plant utilizing IS process (IS plant) are investigated. Furthermore, design considerations to comply with the requirements are suggested and the technical feasibility of the design considerations is evaluated. The evaluation results for a reference plant showed that safe distance determined by the chemical plant regulation against combustible gas and hazardous chemical leakages comply with the plant layout design. Furthermore, the results demonstrated the feasibility of IS plant construction under non-nuclear regulation by showing that the tritium concentration in IS plant can be maintained below the regulation limit and reactor normal operation can be achieved during abnormal conditions in the IS plant. These results clarified that design considerations suggested for coupling the IS plant to HTGR are reasonably practicable. The proposed criteria can be used not only for coupling hydrogen production plants but also for other chemical plants such as steam reforming plants, etc. 相似文献