DETERMINATION OF THE COMPLEX OF THERMOPHYSICAL PROPERTIES OF BORIC ACID WATER SOLUTIONS AT PARAMETERS CHARACTERISTIC FOR VVER EMERGENCY MODE

A. Shlepkin, A. Morozov, A. Sakhipgareev, D. Kalyakin
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Abstract

The article presents the results of experimental studies of the thermophysical (density, viscosity) and physicochemical (degree of acidity - pH) properties of water solutions of boric acid. A review of the available literature data on the effect of the properties of boric acid solutions on heat removal from the reactor core is presented. It has been established that the available information is very general and does not cover the entire range of parameters (temperature, pressure, acid concentration) characteristic of a possible emergency at a nuclear power plant with a VVER reactor. Methods and facilities for conducting experimental studies are described. The results of experimental studies are presented. The density of aqueous solutions of boric acid with a concentration of 2.5-450 g/kg H2O at a temperature of 25-130 °C was determined. The dependence of the investigated characteristic on temperature and concentration was also obtained. The results of an experimental study of the kinematic viscosity of water solutions of boric acid with a concentration of 2.5-200 g/kg H2O at a temperature of 25-90 °C were obtained. The total error in measuring the viscosity of aqueous solutions of boric acid did not exceed 2 %. The pH values of water solutions of boric acid in the temperature range 25-50 and concentrations of 2.5-450 g/kg H2O were determined. The dependence for calculating the degree of acidity of boric acid is obtained. Experimental data on the thermophysical and physicochemical properties of water solutions of boric acid can be used to refine the results of calculations of emergency heat removal processes in a reactor facility, carried out using both one-dimensional calculation programs and three-dimensional CFD codes.
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应急模式下硼酸水溶液在参数特征下的热物理性质复合体的测定
本文介绍了硼酸水溶液的热物理(密度、粘度)和物理化学(酸度- pH)性质的实验研究结果。综述了硼酸溶液性质对反应器堆芯散热影响的文献资料。可以确定的是,现有的资料非常笼统,并没有涵盖具有VVER反应堆的核电站可能发生紧急情况的全部参数范围(温度、压力、酸浓度)。描述了进行实验研究的方法和设备。给出了实验研究结果。测定了浓度为2.5 ~ 450 g/kg H2O的硼酸水溶液在25 ~ 130℃温度下的密度。还得到了所研究的特性与温度和浓度的关系。对硼酸水溶液在25 ~ 90℃温度下,浓度为2.5 ~ 200 g/kg H2O的运动粘度进行了实验研究。测定硼酸水溶液粘度的总误差不超过2%。测定了硼酸水溶液在25 ~ 50℃、2.5 ~ 450 g/kg H2O浓度范围内的pH值。得到了计算硼酸酸度的依赖关系。硼酸水溶液的热物理和物理化学性质的实验数据可用于改进反应堆设施中使用一维计算程序和三维CFD程序进行的紧急排热过程的计算结果。
本文章由计算机程序翻译,如有差异,请以英文原文为准。
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POSSIBILITY OF APPLICATION OF ZrO2-MgO-CaO CRUCIBLES FOR PRODUCING ALLOY U-10 % Zr CALCULATION ESTIMATION OF THE REQUIRED HEAT GENERATION IN TESTING FUEL ELEMENTS TO ACHIEVE SUPERCRITICAL PARAMETERS OF THE COOLANT UNDER IRRADIATION IN THE RESEARCH NUCLEAR REACTOR FEATURES OF THERMAL HYDRAULICS OF ACTIVE ZONES OF FAST LOW-POWER AND HIGH-POWER SODIUM PRODUCTION REACTORS FOR A CLOSED FUEL CYCLE SYSTEM CALCULATION OF THE STRUCTURAL MATERIALS ACTIVATION BY A FUSION NEUTRON FLUX WITH BPSD CODE HEAT PIPES IN NUCLEAR ENGINEERING
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