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Design and Analysis of 900 MWt Lead-Cooled Fast Reactor

机译:900 MWt铅冷快堆的设计与分析

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A lead-cooled fast reactor system for TRU burning is developed, using TRU-U-Zr metallic alloy fuel. This core has a rated thermal power of 900 MWt (372 MWe). The design and analyses covered in this study include neutronics design, thermal-hydraulics analysis, thermal system design, system mechanical design and analysis, system arrangement, passive decay heat removal system evaluation and safety analysis for ATWS events. The gross and net thermal efficiencies are 44.5% and 41.3%. There are two pumps and eight steam generators and they are arranged to provide a proper room for work space in the top of the reactor head. The lead coolant mass in the reactor pool was estimated to be 7,465 ton and this caused the maximum stress of 125 MPa in the top portion of the containment vessel. But, this is below the currently established limit of 165 MPa. Design challenges inherent in the transmutation reactor due to large burnup reactivity swing and high fast neutron fluence are overcome by the introduction of boron carbide within the tie rods with axial cutbacks of 21.8 cm. The maximum coolant speed turns out to be 1.82 m/s and the maximum fuel temperature is only 703 °C in the rated full power condition. The long-term cooling behavior upon the concurrent occurrence of loss of heat sink and loss of flow, the hot pool temperature is maintained below the design limit of 650°C thanks to the improved decay heat removal design with heat transfer enhancement mechanisms. The analysis of ATWSs in the investigated core does not reveal any problem in the view point of fuel temperature, cladding temperature and hot pool temperature. In conclusion, the 900 MWt LFR system in this study does not pose any significant concern except for the seismic loading due to large coolant density and the verification of newly introduced design resolutions for a long-term decay heat removal.
机译:使用TRU-U-Zr金属合金燃料开发了用于TRU燃烧的铅冷快堆系统。该磁芯的额定热功率为900 MWt(372 MWe)。本研究涵盖的设计和分析包括中子学设计,热工液压分析,热系统设计,系统机械设计和分析,系统布置,被动衰减除热系统评估以及ATWS事件的安全性分析。总和净热效率分别为44.5%和41.3%。有两个泵和八个蒸汽发生器,它们的布置是为了在反应堆顶部提供适当的工作空间。估计反应堆池中的铅冷却剂质量为7,465吨,这在安全壳顶部造成了125 MPa的最大应力。但是,这低于当前确定的165 MPa极限。通过在拉杆中引入碳化硼(轴向缩减21.8厘米),克服了由于burn燃反应性大和高中子注量引起的the变反应器固有的设计挑战。在额定满功率条件下,最大冷却液速度为1.82 m / s,最高燃油温度仅为703°C。散热片和流量损失同时发生时的长期冷却性能,由于采用了带有传热增强机制的改进的衰减式除热设计,因此使水池的温度保持在650°C的设计极限以下。从燃料温度,包层温度和热池温度的角度出发,对所研究岩心中ATWS的分析没有发现任何问题。总之,本研究中的900 MWt LFR系统除了由于大的冷却液密度和承受长期衰减的热量而新引入的设计分辨率的验证所引起的地震载荷外,没有引起任何重大的关注。

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