核研究设施反蒸汽发生器热水力稳定性计算分析

A. Semchenkov, I. Kustova, O. Nikel, Y. Kabanov
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引用次数: 0

摘要

蒸汽-水回路中循环的稳定性,即热工参数在运行扰动特性的可接受范围内的保存,在很大程度上决定了蒸汽发生器本身的可靠性。在一定条件下,沸腾装置中会出现脉动压力、脉动流量和脉动温度。首次在直通式锅炉的制造过程中遇到了波纹,并且流动不稳定性对设备设计的有害影响导致需要对该问题进行详细研究。本文对MBIR核研究设施(NRF)反蒸汽发生器(OPG)的热工稳定性进行了计算分析。需要进行这样的研究是因为OPG由三个并联的蒸汽发生模块组成。在这种设计下,水流速率可能出现脉动,包括在单独的蒸汽发生通道中出现倾覆流速。为了避免这种情况,有必要在每个OPG模块的进口处进行节流,因此,在本研究中,确定了扼流圈的水力阻力。研究方法是基于使用反蒸汽发生器的数值热工模型,该模型是通过认证的热工设计代码HYDRA-IBRAE/LM/V1制作的。在省煤器和过热段的OPG RNU MBIR有扭曲的热交换强化器,在相对于热交换管束的纵向和横向方向上引导水和蒸汽。这种情况需要一种特殊的方法来计算沿OPG模块路径的水力阻力和传热系数。计算模型建立后,需要对其进行验证,由于NRF MBIR的OPG设计与BOR-60反应堆的OPG设计相似,因此使用OPG BOR-60上获得的实验数据进行验证。通过对模块节流后OPG NRF MBIR正常工作模式的计算,证实了在这些模式下流量没有波动。
本文章由计算机程序翻译,如有差异,请以英文原文为准。
COMPUTATIONAL ANALYSIS OF THERMAL HYDRAULIC STABILITY REVERSE STEAM GENERATOR NUCLEAR RESEARCH FACILITY MBIR
The stability of the circulation in the steam-water circuit, that is, the preservation of the thermohydraulic parameters within acceptable limits for perturbations characteristic of the operation, largely determines the reliability of the steam generator itself. Under certain conditions, pulsating pressure, flow and temperature pulsations may appear in boiling apparatus. For the first time, ripples were encountered during the creation of once-through boilers, and the harmful effect of flow instability on the apparatus design led to the need for a detailed study of the problem. In this work, a computational analysis of the thermal-hydraulic stability of the reverse steam generator (OPG) of the MBIR nuclear research facility (NRF) is carried out. The need for such a study is due to the fact that the OPG consists of three parallel connected steam generating modules. With such a design, water flow rate pulsations may appear, including with overturning flow rates in separate steam-generating channels. To avoid this, it is necessary to conduct throttling at the inlet to each OPG module, therefore, in this study, the hydraulic resistance of the chokes is determined. The research methodology is based on the use of a numerical thermohydraulic model of a reverse steam generator, made by means of a certified thermohydraulic design code HYDRA-IBRAE/LM/V1. The OPG RNU MBIR at the economizer and superheating sections has twisted heat exchange intensifiers that direct water and steam both in the longitudinal and transverse directions relative to the bundle of heat exchange tubes. This circumstance required a special approach in calculating the hydraulic resistance and heat transfer coefficients along the path of the OPG modules. After the creation of the computational model, it had to be verified, and since the design of the OPG of the NRF MBIR is similar to the design of the OPG of the BOR-60 reactor, the experimental data obtained on the OPG BOR-60 were used for verification. The calculations of the normal operation modes of the OPG NRF MBIR after the throttling of the modules confirmed the absence of fluctuations in the flow rate in these modes.
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