Development of a thermal-hydraulic analysis code for primary system of an integrated small modular pressurized water reactor

被引：0
|
作者：
Wang, Dongqing [1 ]
Chen, Huandong [1 ]
Chen, Jiayue [1 ]
Zhan, Dekui [2 ]
Xia, Shaoxiong [2 ]
机构：
[1] Sun Yat Sen Univ, Sino French Inst Nucl Engn & Technol, Zhuhai 519082, Guangdong, Peoples R China
[2] China Nucl Power Technol Res Inst Co Ltd, Reactor Engn & Safety Res Ctr, Shenzhen 518031, Peoples R China
来源：
ANNALS OF NUCLEAR ENERGY | 2021年 / 152卷
基金：
中国博士后科学基金; 国家重点研发计划;
关键词：
Thermal-hydraulic analysis code; Primary system; IRIS; Sub-channel model; Helically coiled steam generator model; STEAM-GENERATOR; TRANSIENT ANALYSIS; HEAT-TRANSFER; FLOW; MODEL; SIMULATION; DESIGN; TUBES; CORE; DROP;
D O I：
10.1016/j.anucene.2020.108019
中图分类号：
TL [原子能技术]; O571 [原子核物理学];
学科分类号：
0827 ; 082701 ;
摘要：
In this study, a thermal-hydraulic analysis code has been developed for primary system of the integrated small modular pressurized water reactor IRIS (International Reactor Innovative and Secure). Numerical model of the primary system has been established, and characteristics of equipment and layout are considered. The sub-channel model is used for performance analysis of hot channel in the core. In modeling of the helically coiled steam generator, effects of secondary flow inside coiled tubes are taken into account. Based on the model established, the simulation code THAS (Thermal-Hydraulic Analysis code of SMRs) has been developed. To benchmark this code, steady state performance of the system has been calculated and compared with design parameters as well as results obtained with RELAP5. Furthermore, transient performance of the system is also simulated and compared with RELAP5. The comparison presents a good agreement, which confirms simulation capacity and accuracy of the THAS code. (C) 2020 Elsevier Ltd. All rights reserved.
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页数：13
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