共查询到15条相似文献,搜索用时 250 毫秒
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以基于密度锁的非能动余热排出系统(PRHRS)为研究背景,实验验证了密度锁自平衡启动方案的可行性。结果表明:主回路流量接近平衡流量启动PRHRS时,密度锁内冷热流体温度分界面将在不平衡力作用下向上或向下移动,减小或增大了余热排出回路重位压差,使密度锁内冷热流体温度分界面在新的位置达到受力平衡,最终实现密度锁的自平衡启动,以及余热排出回路与主回路的隔离。依据一维连续性方程、能量方程及动量方程建立数学模型,用Matlab语言编程,对密度锁启动过程进行了数值模拟分析,证明了密度锁自平衡启动方案合理、有效。计算值与实验值符合较好,用该程序可较好地模拟密度锁自平衡启动过程中系统的瞬态运行特性。 相似文献
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以应用密度锁的非能动余热排出系统为背景,结合实验研究和理论分析,对密度锁自平衡启动的运行特性及可行性进行研究。结果表明:自平衡启动可分为关阀预热和开阀平衡两个阶段,在这两个阶段内能分别实现密度锁“关闭”所必需满足的两个条件,达到隔离非能动余热排出回路与主回路的目的。在关阀预热阶段,密度锁借助其特殊结构,有效地控制了传热方式转变点的位置,促进了热/冷流体交界面的形成;在开阀平衡阶段,借助其水力平衡的自稳定特性,有效地控制了热/冷流体交界面的移动,建立了密度锁内的水力平衡。所得结果充分证明了自平衡启动方法的可行性。 相似文献
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模块化压水堆非能动余热排出系统运行特性分析研究 总被引:2,自引:0,他引:2
针对初步设计的非能动余热排出系统方案并结合模块化反应堆的结构和运行特点,对非能动余热排出系统进行合理的控制体和节点划分并建立数学物理模型,采用数值迭代方法和通用热工水力分析程序,分析非能动余热排出系统的瞬态热工水力特性。结果表明,反应堆发生断电事故后,系统自然循环可以很快建立;在非能动余热排出过程中,换热器中二次侧始终为液相,没有发生流动不稳定;应急冷却器换热面积在一定范围内变化对系统余热排出能力没有显著影响。 相似文献
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非能动余热排出系统依靠本身的自然循环特性,应能够在较长时间内提供对堆芯的冷却,保证反应堆的安全。提出一种非能动空气冷却余热排出系统(PRHRS)方案,利用应急冷却水箱作为中间缓冲设备,既可以满足事故初期快速冷却的要求,又能保证非能动余热排出系统在相当长一段时间内的可靠运行。基于自然循环系统特性对所设计的PRHRS系统进行设计计算,并使用RELAP5程序对全厂断电事故下反应堆停堆后PRHRS投入运行的过程进行仿真,以验证设计的合理性。反应堆热工水力动态特性的结果表明,该系统可通过自然循环排出堆芯余热,保证堆芯安全。 相似文献
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Young-Jong Chung Hee-Cheol KimBub-Dong Chung Moon-Ki ChungSung-Quun Zee 《Annals of Nuclear Energy》2006
An investigation of the thermal hydraulic characteristics and the natural circulation performance in the passive residual heat removal system (PRHRS) for an integral type reactor have been carried out using the VISTA facility and the calculated results using the MARS code, which is a best estimate system analysis code have been compared with the experimental results. The VISTA facility consists of the primary, secondary, and the PRHRS circuits, to simulate the SMART design verification program. The experimental results show that the fluid is well stabilized in the PRHRS loop and the PRHRS heat exchanger accomplishes well its functions in removing the transferred heat from the primary side in the steam generator as long as the heat exchanger is submerged in the water in the emergency cooldown tank (ECT). The decay heat and the sensible heat can be sufficiently removed from the primary loop with the operation of the PRHRS. The MARS code predicts reasonably well the characteristics of the natural circulation in the PRHRS. From the calculation results, most of the heat transferred from the primary system is removed at the PRHRS heat exchanger by a condensation heat transfer. 相似文献
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《Journal of Nuclear Science and Technology》2013,50(5):703-713
Experiments on the heat transfer characteristics and natural circulation performance of the passive residual heat removal system (PRHRS) for the SMART-P have been performed by using the high temperature/high pressure thermal-hydraulic test facility (VISTA). The VISTA facility consists of the primary loop, the secondary loop, the PRHRS loop, and the auxiliary systems to simulate the SMART-P, a pilot plant of the SMART. The primary loop is composed of the steam generator (SG) primary side, a simulated core, a main coolant pump, and the loop piping, and the PRHRS loop consists of the SG secondary side, a PRHRS heat exchanger, and the loop piping. The natural circulation performance of the PRHRS, the heat transfer characteristics of the PRHRS heat exchangers and the emergency cooldown tank (ECT), and the thermal-hydraulic behavior of the primary loop are intensively investigated. The experimental results show that the coolant flows steadily into the PRHRS loop and that the heat transfers through the PRHRS heat exchanger and the emergency cooldown tank are sufficient enough to enable a natural circulation of the coolant. The results also show that the core decay heat can be sufficiently removed from the primary loop with an operation of the PRHRS. 相似文献
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Hyun-Sik Park Ki-Yong ChoiSeok Cho Sung-Jae YiChoon-Kyung Park Moon-Ki Chung 《Annals of Nuclear Energy》2008
Natural circulation characteristics of an integral type reactor during the operation of a passive residual heat removal system (PRHRS) following a safety related event has been experimentally investigated by using the VISTA facility. A PRHRS actuation trip signal is generated by a high power trip signal following a steam flow increasing event. The experimental results show that the single-phase coolant flows steadily in the primary loop by a natural convection process and that it effectively removes the decay heat from the core through a steam generator during the PRHRS operation. The heat transfers through the PRHRS heat exchanger and the emergency cooldown tank (ECT) are sufficient enough to enable a two-phase natural circulation of the coolant in the PRHRS loop. 相似文献
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浮动式核电站长期在海洋环境中运行,各系统都会受到海洋运动条件的影响。非能动余热排出系统(PRHRS)可在核电站发生全厂断电事故的情况下带出堆芯衰变余热,防止堆芯熔化,是重要的反应堆辅助系统。本文以一种采用海水作为最终热阱的浮动式核电站作为研究对象,分别设计了一回路和二回路PRHRS,开展了静止和摇摆条件下反应堆系统发生全厂断电事故的计算,对两种PRHRS在静止和摇摆条件下的运行特性进行了分析。研究表明,静止条件二回路PRHRS具有更强的带热能力,摇摆条件下一回路PRHRS的带热能力更加稳定。 相似文献
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提出了一种新型非能动余热排出系统(PRHRS)设计方案,该方案以高位水箱为最终热阱,采用在蒸汽发生器二次侧建立自然循环的方式间接地带走堆芯余热。以大亚湾核电站主冷却剂系统为载体,用RELAP5/MOD3.2程序分析了全厂断电事故下,PRHRS的运行特性。结果表明:事故发生后,余热排出系统内可较快地建立起循环流动,带走蒸汽发生器二次侧热量,在一段时间内保证反应堆安全,证明系统设计合理、有效。并分析了换热器布置高度、系统投入时间及换热面积对余热排出系统运行特性的影响。 相似文献