EXPERIMENTAL JUSTIFICATION OF DESIGN CHARACTERISTICS OF STEAM GENERATOR RP BREST-OD-300

V. Grabezhnaya, A. Mikheyev, A. Alekhin, A. Kryukov, A. Tikhomirov
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Abstract

The project BREST-OD-300 reactor plant (RP) with a fast neutron reactor and a lead coolant in the primary circuit is being developed in NIKIET JSC. As a steam generator (SG), a helical-type steam generator with coiled tubes with subcritical pressure water in the second circuit is considered. To substantiate the design characteristics of the secondary coolant at the State Research Center of the Russian Federation - IPPE, thermohydraulic tests of various SG models were carried out at the SPRUT stand Initially, tests were carried out on a model of a coiled steam generator consisting of two three-tube modules with a longitudinal lead flow around a three-tube bundle of coiled tubes. The influence of operating parameters on thermohydraulic characteristics and hydrodynamic stability is shown in the case of operation of one module, as well as in the joint operation of two models in the investigated range of operating parameters. At the second stage, tests of a standard steam generator model were carried out with lead flowing around 18 heat exchange tubes. In the multitube model, the downward movement of the heating coolant took place with the flow around the bundle of heat transfer tubes close to the transverse flow. Data were obtained on the hydrodynamic stability of steam generating tubes and the entire model as a whole when operating in the entire range of changes in operating parameters, which are necessary for creating a databank and further verification of calculation codes describing the ongoing thermohydraulic processes. During the tests in both models of the steam generator, there were no noises inherent in unstable operating modes of the circuit. No pulsations of water and steam temperature were found, respectively, in the inlet and outlet collectors. At high lead temperatures, the temperature of the superheated steam was always close to the lead inlet temperature. A series of works devoted to the study of heat transfer from the side of a lead coolant with a transverse flow around a package of heat exchange tubes in normal heat transfer modes and with freezing of lead has been completed. Studies have been carried out on the effect of oxygen concentration in lead on heat transfer.
rp - brest-od-300蒸汽发生器设计特性的实验论证
项目BREST-OD-300反应堆工厂(RP),一个快中子反应堆和铅冷却剂的一次回路正在NIKIET JSC开发。作为蒸汽发生器,我们考虑了一种螺旋式螺旋管蒸汽发生器,在第二回路中有亚临界压力的水。为了证实俄罗斯联邦国家研究中心(IPPE)的二次冷却剂的设计特点,在SPRUT展台上对各种SG模型进行了热水力试验。首先,对一个由两个三管模块组成的盘状蒸汽发生器模型进行了试验,该模型在三管束的盘状管周围有纵向引线流。分析了运行参数对单模块运行和两个模型在运行参数范围内联合运行时的热水力特性和水动力稳定性的影响。在第二阶段,对标准蒸汽发生器模型进行了测试,铅在18个换热管周围流动。在多管模型中,加热冷却剂的向下运动发生在靠近横向流动的换热管束周围。在整个运行参数变化范围内运行时,获得了蒸汽发生管和整个模型的水动力稳定性数据,这些数据对于创建数据库和进一步验证描述正在进行的热水力过程的计算代码是必要的。在两种型号的蒸汽发生器的测试过程中,电路的不稳定工作模式没有固有的噪声。在进口和出口集热器中分别没有发现水和蒸汽温度的脉动。在高铅温下,过热蒸汽的温度始终接近铅入口温度。本文完成了铅冷却剂在正常换热模式下,在铅的冻结条件下,在一组换热管周围横向流动的情况下,从铅冷却剂侧面传热的一系列研究工作。对铅中氧浓度对传热的影响进行了研究。
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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