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HTR-10超高温运行的初步物理热工设计

Preliminary Physical Design and Thermal Hydraulic Design on HTR-10 Operating in Higher Outlet Temperature
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摘要 高温气冷堆(HTGR)已被国际核能领域专家列入第四代先进堆型之一。由于其固有安全性好、出口温度高,在发电、供热、制氢、石油精炼、煤液化、直接还原炼铁等领域都有广泛的应用前景和潜力,可以为降低温室气体排放、应对气候变化、从一次能源的源头排除碳引入、大幅减少中国能源化工工艺带来的局部污染物(酸性气体、粉尘等)等作出重要贡献。清华大学核能与新能源技术研究院成功设计、建造和运行了10 MW高温气冷堆实验堆(HTR-10),并建造了球床模块式高温气冷堆核电站示范工程(HTR-PM),在高温气冷堆研究领域积累了丰富的经验,取得了很多的成果。本文重点介绍基于现有的结构设计和燃料元件设计,利用HTR-10进一步提升冷却剂出口温度、实现超高温运行的物理热工设计研究,阐述其主要的研究进展及取得的成效,为实现具有固有安全性的超高温气冷堆的设计、建造和运行提供参考和依据。 High Temperature Gas-cooled Reactor(HTGR) is recognized as a candidate for the Generation Ⅳ nuclear energy system technology.With its well-known inherent safety features and high outlet temperature, the HTGR is expected to be widely used for power generation,heat supply, hydrogen production, petroleum refinement,coal liquefaction and direct-reduction iron making.It can make important contributions to reducing greenhouse gas emissions, coping with climate change, eliminating the introduction of carbon from the source of primary energy,and greatly mitigating local pollutants(acid gases, dust,etc.) brought by China’s energy and chemical processes.The Institute of Nuclear and New energy technology(INET) of Tsinghua University successfully designed,built and operated the 10 MW High Temperature Gas-cooled Reactor Experimental Reactor(HTR-10);A commercial-scale 200 MWe High Temperature gas-cooled Reactor Pebble-bed Module project(HTR-PM) has also been designed and constructed supported by the National S&T Major Project. The HTR-PM is now in the commissioning phase and the fuel loading is expected soon.With decades of research and practice, the INET of Tsinghua University has accumulated abundant experience in the HTGR technology. Supported by the National Key R&D Program of China, further theoretical research and experimental verification on the core key technology, IHXpipe technology and so on are now being carried out, to maintain China’s leading position in the field of HTGR technology. This article introduces thephysical thermal design research of HTR-10 carried out by the project team based on its existing structural design and fuel element design to further increase the coolant outlet temperature and achieve very high temperature operation, and summarize the main research progress. The project research work can provide reference and basis for the design, construction and operation of very high temperature gas-cooled reactors with inherent safety in the future.
作者 郑艳华 夏冰 解衡 王捷 ZHENG Yanhu;XIA Bing;XIE Heng;WANG Jie(Institute of Nuclear and New Energy Technology,Collaborative Innovation Center of Advanced Nuclear Energy Technology,Key Laboratory of Advanced Reactor Engineering and Safety of Ministry of Education Tsinghua University,Beijing 100084)
出处 《中国基础科学》 2021年第3期16-20,共5页 China Basic Science
基金 国家重点研发计划项目(2018YFB1900500)。
关键词 HTGR HTR-10 物理设计 热工水力设计 失冷失压事故 HTGR HTR-10 physical design thermal hydraulic design DLOFC accident
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