Сriterion用于确定反应堆堆芯发生热声不稳定的条件的方法

IF 0.5 Q4 PHYSICS, NUCLEAR
V.A. Kondratuk, O.A. Dorozh, V.I. Filatov, T.V. Bibik
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引用次数: 0

摘要

研究的主题是核反应堆堆芯冷却剂的热声不稳定性(TAI)。堆芯TAI的发生会对反应堆内部结构产生高频、高振幅的循环载荷,可能是燃料元件密封性丧失的原因之一。提出了一种确定核反应堆堆芯在运行模式、瞬态模式和应急模式下冷却剂TAI区域边界的判据方法。在此基础上,确定了冷却液中出现TAI的区域,并制定了TAI的判定标准。TAI面积的无因次确定标准是根据反应堆堆芯入口处冷却剂的放热速率、流速和焓来确定的。采用无量纲参数格式,确定了反应堆相对功率大于0.25、冷却剂相对流量小于0.75时,水冷堆堆芯TAI面积。
本文章由计算机程序翻译,如有差异,请以英文原文为准。
СRITERION METHOD FOR DETERMINING THE CONDITIONS FOR OCCURRENCE OF THERMOACOUSTIC INSTABILITY IN THE REACTOR CORE
The subject of research is the thermoacoustic instability (TAI) of the coolant of a nuclear reactor core. The occurrence of TAI in the reactor core leads to high-frequency and high-amplitude cyclic loads on internal reactor structures and can be one of the reasons for the loss of tightness of fuel elements. A criterion method has been developed for determining the boundaries of the coolant TAI area in the nuclear reactor core under operating, transient and emergency modes. Based on the developed method, the occurrence of TAI area in the coolant was determined, with the criteria of TAI being formulated. A dimensionless determining criterion of the TAI area was justified depending on the rate of heat release, flow rate and enthalpy of the coolant at the entry to the reactor core. Applying the format of dimensionless parameters, the area of TAI of a water-cooled reactor core has been determined, with the relative power of the reactor being more than 0.25 and the relative flow rate of the coolant being less than 0.75.
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来源期刊
CiteScore
0.70
自引率
50.00%
发文量
0
审稿时长
2-4 weeks
期刊介绍: The journal covers the following topics: Physics of Radiation Effects and Radiation Materials Science; Nuclear Physics Investigations; Plasma Physics; Vacuum, Pure Materials and Superconductors; Plasma Electronics and New Methods of Acceleration.
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