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Scaling analysis of passive resedual heat exchanger ZHANG Pan1, LIU Yusheng2, WEN Lijing3, and XU Chao4 1.Nuclear and Radiation Safety Center, NO.54, HongLianNanCun, Haidian, Beijing, 100082, China (13341177785@163.com) 2.Nuclear and Radiation Safety Center, NO.54 ,HongLianNanCun, Haidian, Beijing, 100082, China (liuyusheng8866@163.com) 3.Nuclear and Radiation Safety Center, NO.54, HongLianNanCun, Haidian, Beijing, 100082, China (wenlj718@sina.com) 4.Nuclear and Radiation Safety Center, NO.54, HongLianNanCun, Haidian, Beijing, 100082, China (seanwillian@163.com) Abstract: When the station blackout accident happens on the pressurized water reactor nuclear power plant, the reactor core decay heat could be transferred to the second circuit by the natural circulation which between core and steam generator (SG). When the water level on the SG secondary side drops to the low level, the passive residual heat removal system (PRHR) will put into operation. In later time, the PRHR system plays a leading role in carrying out the core decay heat. Therefore, the heatexchangecapacity of PRHR is an important factor which affecting the safety of the reactor. In order to verify the functionality of security systems on the new advanced pressurized water reactor technology, it is usually needed to carry out large-scale engineering verification tests. And in order to ensure that important phenomenon between prototype plant and test are similar, it is needed to carry out the scaling analysis. Taking the station blackout accident of passive nuclear power plant as research background, this paper uses H2TS method to take the scaling analysis. It focuses on the thermal-hydraulic behavior of PRHR system, and obtains the similar criterion between the prototype PRHR system and test PRHR system under the station blackout accident. It also carries out the distortion analysis. The conclusions gained are as follows. To ensure height ratio and flow area ratio of the passive residual heat removal heat exchanger (PRHR HX) are consistent with the integral system ratios, the geometric shape and arrangement type of heat transfer tubes are same with prototype, it is easy to establish similarity between test and prototype. It uses the same physical properties method to simulate the station blackout accident, the exchange capacity of the PRHR system has some distortion. But the heat exchange capacity of PRHR HX in the nuclear power plant has some design margin, you can adjust the heat exchanger pipe diameter and number to ensure PRHR HX is still able to meet the needs of core cooling function, even it has some distortion. Keyword: scaling analysis;PRHR HX; station blackout; similar criterion
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