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A Transient Simulation Test Rig for Heat Pipe Cooled Space Nuclear Reactors

机译:热管冷却空间核反应堆的瞬态仿真试验台

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The purpose of this study is to design and determine the physical requirements for the construction of a robust test facility for a small space nuclear power system. The test rig will be used to simulate a 1-10kWe nuclear reactor, its electrical generation, and heat removal capabilities. This simulator will be used to explore, test and understand the steady-state and transient operation capabilities of small space nuclear power systems. Various transient modes will be simulated including start up, shutdown, and re-start plus various accident conditions such as loss of heat pipe cooling and loss of radiator cooling. Currently, the system is planned to operate on a variable, electrical heat source directly connected to heat pipes. The heat pipes are to be stainless steel with a sodium or other working fluid. These heat pipes will then pass through a variable heat removal simulator for the shield and then be connected to a power conversion simulator or actual power conversion technologies. The power conversion simulator is then connected to a radiator. The radiator is a water based heat pipe network using fins and connecting plates to approximate the shape of a cone with ridges.
机译:这项研究的目的是设计和确定为小型太空核动力系统建造坚固的测试设施的物理要求。该试验台将用于模拟1-10kWe核反应堆,其发电量和排热能力。该模拟器将用于探索,测试和了解小型空间核动力系统的稳态和瞬态运行能力。将模拟各种瞬态模式,包括启动,关闭和重新启动,以及各种事故情况,例如热管冷却损失和散热器冷却损失。当前,该系统计划在直接连接到热管的可变电热源上运行。热管应为带有钠或其他工作流体的不锈钢。然后,这些热管将通过用于屏蔽的可变排热模拟器,然后连接到功率转换模拟器或实际的功率转换技术。然后将功率转换模拟器连接到散热器。散热器是一个基于水的热管网络,它使用散热片和连接板来近似带有脊的圆锥形状。

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