试验研究了核电站冷却剂沸腾过程中硼酸在蒸汽中的溶解度特征

A. Sakhipgareev, A. Shlepkin, A. Morozov
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引用次数: 0

摘要

本文考虑了硼酸在浓度为16 ~ 440 g/kg H2O、压力为0.1 ~ 0.3 MPa的蒸汽中的溶解度的实验研究结果。对硼酸在蒸汽中的溶解度的文献数据的分析表明,结果并没有涵盖具有WWER的核电厂可能出现的紧急情况的典型参数(温度、压力、硼酸浓度)的整个范围。本文对试验装置进行了描述。得到的实验结果证实了文献资料中硼酸浓度的变化符合线性规律。沸水冷却剂液汽两相间H3BO3分布依赖关系的适用范围扩大到浓度为440 g/kg H2O,接近硼酸在0.3 MPa压力下在水中的溶解度极限。所获得的实验数据可用于考虑被动安全系统运行的WWER核电站的应急计算。
本文章由计算机程序翻译,如有差异,请以英文原文为准。
EXPERIMENTAL STUDY OF THE FEATURES OF PROCESS OF SOLUBILITY OF BORIC ACID IN STEAM DURING OF BOILING OF THE COOLANT OF THE WWER IN CASE OF ACCIDENT
The results of experimental studies of the solubility of boric acid in steam in the concentration range of 16-440 g/kg H2O and the pressure range of 0.1-0.3 MPa is considered in the article. An analysis of the literature data on the solubility of boric acid in steam showed that the results do not cover the entire range of parameters (temperature, pressure, concentration of boric acid) typical of a possible emergency situation at NNPs with the WWER. In paper the test facility is described. The obtained experimental results confirm the data available in the literature that the change in the concentration of boric acid in steam is described by a linear law. The range of application of the dependence of the distribution of H3BO3 between the liquid and steam phases of the boiling coolant has been expanded to a concentration of 440 g/kg H2O, which is close to the solubility limit of boric acid in water at a pressure of 0.3 MPa. The obtained experimental data can be used in the calculating of the emergency at nuclear power plants with WWER, taking into account the operating of passive safety systems.
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