THERMAL AND HYDRAULIC STUDIES OF A HIGH-TEMPERATURE NPP FOR HYDROGEN PRODUCTION AND OTHER TECHNOLOGICAL APPLICATIONS

A. Sorokin, A. Ivanov, Yu. A. Kuzina, A. Morozov, N. Denisova
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Abstract

An important problem determining the development of clean energy is the involvement of hydrogen in the fuel cycle. At present, the main method of hydrogen production is steam methane conversion. In the long term, large-scale hydrogen production, this method is not viable due to the consumption of non-renewable resources and the emission of greenhouse gases. Alternative methods of hydrogen production by water splitting methods using thermochemical or electrolysis processes require a high-temperature heat source. Nuclear reactors can serve as the most widely used high-temperature heat sources. The performed neutron-physical and thermophysical studies have shown that there is a fundamental possibility to provide the required parameters of a high-temperature (900-950 °C) with a 600 MW (thermal) fast neutron reactor with a sodium coolant for hydrogen production. It’s possible on the basis of one of the thermochemical cycles or high-temperature electrolysis with a high coefficient of thermal utilization of energy. It is shown that the temperature regime of core fuel elements is determined by a large number of parameters that have a regular and statistical nature. The developed methodology and numerical program allows to take into account, in the fuel assemblies shaped during the campaign, the effect on the temperature distribution of the fuel element cladding and temperature irregularities along the fuel element perimeter in the interchannel exchange fuel assembly, the random distribution of channel cross-sections and the heat generation of fuel elements using the Monte Carlo method, also other factors. For various reactor operating regimes, zones with stable temperature stratification with large gradients and temperature fluctuations have been identified. The results obtained make it possible to judge the amplitude and frequency characteristics of temperature pulsations in these potentially dangerous areas. The relative small size, the type of coolant, the choice of fissile material and structural materials make it possible to create a reactor with inherent properties that ensure increased nuclear and radiation safety.
用于制氢和其他技术应用的高温核电站的热力和水力研究
决定清洁能源发展的一个重要问题是氢在燃料循环中的参与。目前,主要的制氢方法是蒸汽甲烷转化。从长远来看,大规模制氢,由于不可再生资源的消耗和温室气体的排放,这种方法是不可行的。采用热化学或电解工艺的水裂解制氢的替代方法需要高温热源。核反应堆是应用最广泛的高温热源。所进行的中子物理和热物理研究表明,使用钠冷却剂生产氢气的600兆瓦(热)快中子反应堆有可能提供所需的高温(900-950°C)参数。这是可能的基于一个热化学循环或高温电解具有很高的能量热利用系数。结果表明,堆芯燃料元件的温度状态是由大量具有规律性和统计性质的参数决定的。所开发的方法和数值程序允许考虑在运动期间成形的燃料组件中,对燃料元件包壳温度分布的影响和沿通道间交换燃料组件中燃料元件周长的温度不规则性,通道横截面的随机分布和使用蒙特卡罗方法的燃料元件产热,以及其他因素。对于不同的反应堆运行状态,已经确定了具有大梯度和温度波动的稳定温度分层的区域。所得结果使判断这些潜在危险区域温度脉动的幅度和频率特性成为可能。相对较小的尺寸、冷却剂的类型、裂变材料和结构材料的选择,使制造具有固有特性的反应堆成为可能,从而确保提高核与辐射安全。
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