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research-article

Numerical simulation research on the performance of SCWR fuel rod

[+] Author and Article Information
Changbing Tang

Science and Technology on Reactor System Design Technology Laboratory, Nuclear Power Institute of China No. 328, First Section of Changshun Avenue, Shuangliu District, Sichuan, China
changbingtang0623@163.com

Shuo Xing

Science and Technology on Reactor System Design Technology Laboratory, Nuclear Power Institute of China No. 328, First Section of Changshun Avenue, Shuangliu District, Sichuan, China
154589027@qq.com

Hua Pang

Science and Technology on Reactor System Design Technology Laboratory, Nuclear Power Institute of China No. 328, First Section of Changshun Avenue, Shuangliu District, Sichuan, China
2654805380@qq.com

Ping Chen

Science and Technology on Reactor System Design Technology Laboratory, Nuclear Power Institute of China No. 328, First Section of Changshun Avenue, Shuangliu District, Sichuan, China
chenping_npic@163.com

Yi Zhou

Science and Technology on Reactor System Design Technology Laboratory, Nuclear Power Institute of China No. 328, First Section of Changshun Avenue, Shuangliu District, Sichuan, China
214121048@qq.com

1Corresponding author.

ASME doi:10.1115/1.4038060 History: Received April 09, 2017; Revised September 22, 2017

Abstract

Because of the high temperature and high pressure characteristics of SCWR, the thermal hydraulic performance of SCWR is greatly different from PWR, which makes the current PWR fuel rod performance analysis codes are no longer applicable to SCWR. In this research, the irradiation swelling, irradiation densification, thermal expansion, thermal creep, irradiation creep and irradiation hardening of UO2 pellet were considered, the irradiation swelling, thermal expansion, thermal creep and plastic deformation of stainless steel cladding were considered, the gas conductance and radiant conductance of gap heat transfer were considered, the forced convective heat transfer on the outer surface of cladding was considered. Meanwhile, the irradiation effects and the thermal effects on the materials parameters such as thermal conductivity, specific heat and young's modulus were also considered in this research. With the help of ABAQUS software, the related user-defined subroutines were developed, and the irradiation effects and thermal effects of SCWR fuel were introduced into the numerical simulation, and then completed the analysis of SCWR fuel rods' performance under the steady power conditions. Some reference suggestions for the design and development of SCWR fuel were provided by the establishment of this numerical simulation method.

Copyright (c) 2017 by ASME
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