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Experimental investigation of heat transfer during severe accident of a Pressurized Heavy Water Reactor with simulated decay heat generation in molten pool inside calandria vessel

机译:加压重水反应堆严重事故时传热的实验研究。

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摘要

The present study focuses on experimental investigation in a scaled facility of an Indian PHWR to investigate the coolability of molten corium with simulated decay heat in the simulated calandria vessel. Molten borosilicate glass was used as the simulant due to its comparable heat transfer characteristics similar to prototypic material. About 60 kg of the molten material was poured into the test section at about 1200 degrees C. Decay heat in the melt pool was simulated using four high watt heaters cartridges, each having 9.2 kW. The temperature distributions inside the molten pool, across the vessel wall thickness and vault water were measured. Experimental results obtained are compared with the results obtained previously for no decay heat case. The results indicated that presence of decay heat seriously affects the coolability behaviour and formation of crust in the melt pool. The location and magnitude of maximum heat flux and surface temperature of the vessel also are affected in the presence of decay heat. (C) 2016 Elsevier B.V. All rights reserved.
机译:本研究的重点是在印度PHWR的规模化设施中进行实验研究,以研究模拟的calandria容器中熔融的皮质与模拟衰变热的可冷却性。由于熔融硼硅酸盐玻璃具有与原型材料相似的可比传热特性,因此被用作模拟物。在约1200℃下将约60kg的熔融材料倒入测试部分中。使用四个各自具有9.2kW的高功率加热器筒来模拟熔池中的衰减热。测量了熔池内部,整个容器壁厚和穹顶水的温度分布。将获得的实验结果与先前在无衰减热情况下获得的结果进行比较。结果表明,衰减热的存在严重影响了熔池的冷却性能和结皮的形成。在存在衰减热的情况下,容器的最大热通量的位置和大小以及表面温度也会受到影响。 (C)2016 Elsevier B.V.保留所有权利。

著录项

  • 来源
    《Nuclear Engineering and Design》 |2016年第7期|75-87|共13页
  • 作者单位

    Bhabha Atom Res Ctr, Reactor Engn Div, Bombay 400085, Maharashtra, India;

    Bhabha Atom Res Ctr, Reactor Engn Div, Bombay 400085, Maharashtra, India;

  • 收录信息 美国《科学引文索引》(SCI);美国《工程索引》(EI);美国《生物学医学文摘》(MEDLINE);
  • 原文格式 PDF
  • 正文语种 eng
  • 中图分类
  • 关键词

  • 入库时间 2022-08-18 00:41:52

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