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首页> 外文期刊>Progress in Nuclear Energy >Validation of RELAP5/MOD3.3 for subcooled boiling, flashing and condensation in a vertical annulus
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Validation of RELAP5/MOD3.3 for subcooled boiling, flashing and condensation in a vertical annulus

机译:验证RELAP5 / MOD3.3在垂直环空中的过冷沸腾,闪蒸和冷凝

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Continued development of system analysis codes has resulted in the recovery of conservatisms originally imposed on nuclear power reactors, allowing for an increase in the capacity of commercial nuclear reactors. These codes also play an instrumental role in the design and certification of new reactor systems. With the increased demand for passive natural circulation and gravity driven cooling options, these codes are met with the new challenge of simulating low pressure, low flow conditions. The objective of this work is to demonstrate the effectiveness of the widely used RELAP5/MOD3.3 code to simulate boiling, condensing and flashing flows under such conditions. Two-phase flow data in an internally heated vertical annulus with inner diameter of 19.1 mm and outer diameter of 38.1 mm is utilized for validation of the RELAP5/MOD3.3. The code calculation of pressure, temperature, void fraction, interfacial area concentration, and void weighted gas velocity along the 4.5 m test section is compared with data at five axial locations. In the 2.8 m heated section of the channel the code predictions compare favorably in general, although the error does increase at low system pressure. Beyond the heated length, code predictions of condensation and flashing show more noticeable disagreement along the 1.7 m unheated section. Condensation is consistently under-predicted. Flashing varies from relatively good agreement to complete failure, depending on the conditions at the exit of the heated section. User options related to boiling and condensation are also assessed, and shown to have marginal improvements in some conditions. In general the code consistently predicts the point of net vapor generation too soon along the heated length at low mass flux, over predicts the void fraction at the end of the heated length, and has large scatter in void fraction agreement at the end of the channel. (C) 2016 Elsevier Ltd. All rights reserved.
机译:不断发展的系统分析规范已使最初施加于核动力反应堆的保守性得以恢复,从而使商用核反应堆的能力得以提高。这些规范在新反应堆系统的设计和认证中也发挥了重要作用。随着对被动自然循环和重力驱动的冷却选项的需求不断增加,这些代码也迎来了模拟低压,低流量条件的新挑战。这项工作的目的是证明广泛使用的RELAP5 / MOD3.3代码在这种条件下模拟沸腾,冷凝和闪蒸流动的有效性。使用内部加热的垂直环带中的两相流数据(内径为19.1 mm,外径为38.1 mm)来验证RELAP5 / MOD3.3。将沿4.5 m测试段的压力,温度,空隙率,界面面积浓度和空隙加权气体速度的代码计算与五个轴向位置的数据进行了比较。尽管在低系统压力下误差确实会增加,但在2.8 m的通道加热段中,代码预测总体上可比拟。除加热长度外,冷凝和闪蒸的代码预测显示出在1.7 m的未加热段上的差异更加明显。冷凝始终被低估。根据加热部分出口的情况,闪变从相对好的一致性到完全失败不等。还评估了与沸腾和冷凝有关的用户选项,并显示在某些条件下有很小的改进。通常,代码始终以较低的质量通量始终预测沿加热长度的净蒸汽生成点,过度预测加热长度末端的空隙率,并且在通道末尾的空隙率一致性大分散。 (C)2016 Elsevier Ltd.保留所有权利。

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