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Experimental investigation of temperature and heat distribution across 220 MWe Indian PHWR channel under boil-off condition
Annals of Nuclear Energy ( IF 1.9 ) Pub Date : 2020-09-01 , DOI: 10.1016/j.anucene.2020.107600
Subodh Kumar Yadav , Ravi Kumar , D. Mukhopadhyay , Prasanna Majumdar

Abstract Under very low probability postulated accident like LOCA with unavailability of ECCS, the moderator heat sink maintains the channel integrity by providing adequate cooling. As the cooling is external to channel, the circumferential as well axial temperature gradient exists within the channel internals. An experimental set-up was fabricated to simulate the boil-off condition during a postulated accident in NPP. The experiments were conducted at average fuel bundle temperature 600 °C, 800 °C and 1100 °C with superheated mixture of steam and argon. The minimum and maximum temperature in CT, PT and fuel bundle were diametrically opposite to each other; the circumferential as well axial temperature gradient increased with an increase in bundle temperature. The rate of moderator heat absorption increases with increase in bundle temperature. The moderator was successfully able to prevent a breach in the channel; it proved to be the ultimate heat sink during a postulated LOCA with unavailability of ECCS.

中文翻译:

汽化条件下 220 MWe 印度 PHWR 通道温度和热量分布的实验研究

摘要 在极低概率的假设事故(如 LOCA 和 ECCS 不可用)下,减速器散热器通过提供足够的冷却来保持通道完整性。由于冷却在通道外部,因此通道内部存在周向和轴向温度梯度。制造了一个实验装置来模拟核电厂假定事故期间的蒸发条件。实验在平均燃料束温度 600 °C、800 °C 和 1100 °C 下进行,使用蒸汽和氩气的过热混合物。CT、PT和燃料束的最低和最高温度截然相反;周向和轴向温度梯度随着管束温度的增加而增加。慢化剂吸热率随着束温度的增加而增加。版主成功地阻止了频道的破坏;在 ECCS 不可用的假定 LOCA 期间,它被证明是最终的散热器。
更新日期:2020-09-01
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