期刊论文

Zhao, Pengcheng(zpc1030@mail.ustc.edu.cn)

英文

Annals of Nuclear Energy

0306-4549

2021

154

108112

10.1016/j.anucene.2020.108112

Code validation should be finished firstly. According to the geometrical parameters of steam generator listed in Table 1, flow rates of coolant in different U-tube groups are calculated and shown in Table 2 based on the RF-02 experiment condition of PACTEL facility Kauppinen and Riikonen, 2015. Pressure drop between hot and cold plenum and total heat transfer through steam generator are also obtained. According to the Table 2, pressure drop between hot and cold plenum is −256.08 Pa. Comparing

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The reverse flow is an important phenomenon occurring in inverted U-tube steam generator under natural circulation, which may result the heat accumulating in the first loop and cause serious accident. Thus, researching the flow performance and its influence factors in steam generator is necessary for the safety of nuclear reactor. In this paper, the criterion of reverse flow judgement and flow distribution program are developed firstly. Based on the model of PCATEL (Parallel Channel Test Loop) pressurized water reactor, program validation and c...