首页> 外文学位 >COOLABILITY OF COARSE CORIUM DEBRIS BEDS (REACTOR SAFETY, POST ACCIDENT REMOVAL, VOLUMETRICALLY HEAT BED, NATURAL BOILING POROUS MEDIA).
【24h】

COOLABILITY OF COARSE CORIUM DEBRIS BEDS (REACTOR SAFETY, POST ACCIDENT REMOVAL, VOLUMETRICALLY HEAT BED, NATURAL BOILING POROUS MEDIA).

机译:粗碎屑河床的可塑性(反应堆安全性,事故后清除,体积热床,自然沸腾多孔介质)。

获取原文
获取原文并翻译 | 示例

摘要

Because of a corium-coolant interaction, a bed of volumetrically heated particles submerged in the coolant will be formed either in the vessel or in the cavity under a hypothetic reactor core melt down accident. Hence, coolability of the debris bed is essential to the reactor safety. A large scale test facility with extensive instrumentation was constructed to simulate the coarse corium debris bed. The facility which employed a variable 100 kw DC power generator had a cylindrical test bed 101.6 cm in height and 21.6 cm in diameter. The bed was assembled by packing alternating layers of heaters and stone gravel.; The effects of power distribution, bed depth, submergence, particle shape, and pressure on coolability of debris beds have been investigated. Also, the dryout transient phenomena such as dryout inception behavior, dryout inception position, and dryout propagation in three dimensions have been studied. The results indicate that the dryout delay time is simply related to the applied power. The relationship, called the constant energy line, is useful to uniquely define the incipient dryout heat flux. It also provides a convenient and highly accurate means for the experimental measurement of the incipient dryout heat flux.; A model based on the flooding phenomenon was developed to predict the dryout inception position. The results are encouraging. New functions based on the present data for relative permeabilities of turbulent flow were suggested. With these functions, the theoretical model not only predicts the present dryout data but also successfully predicts the void-fraction data obtained from the cocurrent flow experiment and the sparging experiment.
机译:由于存在皮质冷却剂相互作用,在假设的反应堆堆芯熔化事故下,将在容器中或空腔中形成浸没在冷却剂中的大量加热颗粒床。因此,碎屑床的可冷却性对于反应器的安全至关重要。建造了带有大量仪器的大型测试设施,以模拟粗糙的皮质碎屑床。使用可变的100kw直流发电机的设备具有圆柱形的试验台,其高度为101.6cm,直径为21.6cm。通过填充加热器和石砾的交替层来组装该床。研究了功率分布,床层深度,浸没度,颗粒形状和压力对碎片床可冷却性的影响。而且,已经研究了在三个维度上的变干瞬态现象,例如变干开始行为,变干开始位置和变干传播。结果表明,变干延迟时间仅与施加的功率有关。该关系称为恒定能量线,可用于唯一定义初期变干热通量。它还提供了一种方便且高度准确的方法,用于实验测量初期变干热通量。开发了基于水淹现象的模型来预测变干开始位置。结果令人鼓舞。提出了基于当前数据的湍流相对渗透率的新功能。通过这些功能,理论模型不仅可以预测当前的变干数据,还可以成功地预测从并流实验和喷射实验获得的空隙率数据。

著录项

  • 作者

    HUM, KEANE HSIAN-CHIA.;

  • 作者单位

    Purdue University.;

  • 授予单位 Purdue University.;
  • 学科 Engineering Nuclear.
  • 学位 Ph.D.
  • 年度 1985
  • 页码 172 p.
  • 总页数 172
  • 原文格式 PDF
  • 正文语种 eng
  • 中图分类 原子能技术;
  • 关键词

  • 入库时间 2022-08-17 11:51:10

相似文献

  • 外文文献
  • 中文文献
  • 专利
获取原文

客服邮箱:kefu@zhangqiaokeyan.com

京公网安备:11010802029741号 ICP备案号:京ICP备15016152号-6 六维联合信息科技 (北京) 有限公司©版权所有
  • 客服微信

  • 服务号