Seismic Isolation Scheme Design of 200MW Nuclear Heating Reactor

Nannan Hou, Jianling Dong
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Abstract

Air pollution and the energy problem have become concerned and urgently needed to be solved all over the world in recent years. Coal-fired boilers in industrial parks are an important source of air pollutants. Low temperature heating reactor built in industrial zone is an ideal substitute for coal-fired boiler because of its excellent inherent safety and cleanliness. The new type nuclear heating reactor named NHR200-II was proposed by Institute of Nuclear and New Energy Technology of Tsinghua University in 2015[1]. Compared with the previous generation NHR200, the thermal parameters of NHR200-II are improved which can not only be used for regional heating but also realize the multi-purpose like power supply, steam supply and seawater desalination. And the economic benefits are also greatly improved. The design of NHR200-II is based on the design, construction and operation experience of NHR5 which has maintained running safely up to now and NHR200. The main technical features include three circuit design, integrated layout of primary circuit, full power natural circulation, and automatic self-pressurization. NHR200-II uses the traditional anti-seismic technology at present. However, the requirements of seismic performance of reactors have generally increased after Fukushima disaster. This paper tries to apply seismic isolation in NHR200-II to meet the improved requirements of seismic performance and realize the standardized design by which the magnitude of design ground motion is not restricted in the future. Base isolation, which means setting isolation devices like elastomeric bearings or spherical sliding bearings between the foundation and the superstructure, has been widely applied in normal buildings and bridges, but still needs particular design for nuclear reactors. This paper describes NHR200-II seismic isolation system, which consists of the foundation, raft, isolation layer and the whole nuclear island as superstructure. In addition, the paper also tells the design process of the system, including designing of the raft, selecting of isolators and their layout design based on the environment and mechanical property, etc. And the particular calculation method of the performance parameters and acceptance criteria are also shown in this paper. Finally, the overall design method of seismic isolation is given as a conclusion.
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200MW核加热堆隔震方案设计
近年来,空气污染和能源问题已成为世界各国关注和迫切需要解决的问题。工业园区燃煤锅炉是大气污染物的重要来源。工业园区低温加热堆具有良好的安全性和清洁性,是燃煤锅炉的理想替代品。新型核加热堆NHR200-II由清华大学核能与新能源技术研究所于2015年提出[1]。与上一代NHR200相比,改进了NHR200- ii的热力参数,不仅可用于区域供热,还可实现供电、供汽、海水淡化等多用途。经济效益也大大提高。NHR200- ii的设计是基于NHR5和NHR200的设计、建造和运行经验,NHR5至今一直保持安全运行。主要技术特点包括三路设计、一次电路集成布置、全功率自然循环、自动自增压。NHR200-II采用目前传统的抗震技术。然而,福岛核事故发生后,对反应堆抗震性能的要求普遍提高。本文试图在NHR200-II中应用隔震,以满足提高的抗震性能要求,实现今后不受设计地震动幅度限制的标准化设计。基础隔震是指在基础和上部结构之间设置弹性支座或球面滑动支座等隔震装置,已广泛应用于普通建筑和桥梁中,但对于核反应堆仍需要特殊设计。本文介绍了由基础、筏板、隔震层和整个核岛上部结构组成的NHR200-II型隔震体系。此外,本文还讲述了该系统的设计过程,包括筏板的设计、隔振器的选择以及基于环境和力学性能的隔振器布置设计等。并给出了具体性能参数的计算方法和验收标准。最后给出了隔震的总体设计方法。
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