Preliminary Conceptual Design Study on Supercritical Water-Cooled Reactor CSR1000A with Annular Fuel

XIA Bang-yang; ZHAO Chuan-qi; CAO Liang-zhi; LI Qing; LI Xiang; LI Man-chang

Volume 34 Issue 1

Mar. 2025

Turn off MathJax

Article Contents

Abstract

References

Article Navigation > Nuclear Power Engineering > 2013 > 34(1): 15-18

XIA Bang-yang, ZHAO Chuan-qi, CAO Liang-zhi, LI Qing, LI Xiang, LI Man-chang. Preliminary Conceptual Design Study on Supercritical Water-Cooled Reactor CSR1000A with Annular Fuel[J]. Nuclear Power Engineering, 2013, 34(1): 15-18.

Citation:

PDF( 273 KB)

Preliminary Conceptual Design Study on Supercritical Water-Cooled Reactor CSR1000A with Annular Fuel

1. Science and Technology on Reactor System Design Technology Laboratory, Nuclear Power Institute ofChina, Chengdu, 610041, China;
2. School ofNuclear Science mad Technology, Xi'an Jiaotong University, Xi'an, 710049, China

Received Date: 2012-10-15
Rev Recd Date: 2012-11-09

Available Online: 2025-03-08

Abstract

Abstract

On the basis of the annular fuel for PWR,a new type annular fuel for SCWR has been designed in this paper,which has bigger size than that of PWRs,adopts UO₂ particles instead of fuel pellets and coats heat-barrier material on the surface of the inner cladding.Then a new 1000MWe SCWR design concept CSR1000A has been developed,whose core consists of 163 hexagonal fuel assemblies that are made up with 61 new annular fuels and assembly box.After CSR1000A core evaluation,these core key parameters such as discharge burnup,coolant averaged outlet temperature and maximum fuel cladding temperature are presented.
- Annular fuel,
- SCWR,
- Conceptual design

FullText(HTML)

References(0)

References

Relative Articles

[1]	Zhang Lefu, Huang Tao, Su Haozhan, Gao Yang, Guo Xianglong, Shen Zhao, Chen Kai. Progress and Considerations on Candidate Cladding Materials for Supercritical Water-Cooled Reactors[J]. Nuclear Power Engineering, 2025, 46(1): 183-190. doi: 10.13832/j.jnpe.2025.01.0183
[2]	Su Haozhan, Huang Tao, Zhang Lefu, Chen Kai. Effect of Water Chemistry on the Performance of Alloy 800H in Supercritical Water-cooled Reactor[J]. Nuclear Power Engineering, 2023, 44(5): 267-274. doi: 10.13832/j.jnpe.2023.05.0267
[3]	Li Panxiao, Zhang Zhipeng, Wang Chenglong, Zhang Dalin, Qiu Suizheng, Su Guanghui. Conceptual Design and Physical Analysis of Multi-Purpose Heat Pipe Reactor Prototype[J]. Nuclear Power Engineering, 2023, 44(S2): 133-139. doi: 10.13832/j.jnpe.2023.S2.0133
[4]	Wang Lianjie, Cai Yun, Wang Liangzi, Xia Bangyang, Lou Lei, Zhang Bin, Zhang Ce, Hu Yuying. Preliminary Conceptual Design of Ultra-high Flux Reactor Core with Annular Elements[J]. Nuclear Power Engineering, 2023, 44(2): 227-231. doi: 10.13832/j.jnpe.2023.02.0227
[5]	Yao Lei, Xia Bangyang, Lu Di, Wang Lianjie, Li Xiang, Wang Shiqian, Li Qing. Research on Simplified Assembly and Core Structure Design of SCWR[J]. Nuclear Power Engineering, 2020, 41(4): 45-49.
[6]	Wang Weishu, Hou Yanliang, Xu Weihui, Zhu Xiaojing, Bi Qincheng. Investigation on Nonuniformity of Heat Transfer in Triangular Subchannels of Supercritical Water Cooled Reactor[J]. Nuclear Power Engineering, 2018, 39(3): 33-39. doi: 10.13832/j.jnpe.2018.03.0033
[7]	Zheng Meiyin, Chen Ping, Zhang Dalin, Tian Wenxi, Su Guanghui, Qiu Suizheng. Research on Conceptual Design of Sodium Cooled Standing Wave Reactor[J]. Nuclear Power Engineering, 2018, 39(S1): 79-83. doi: 10.13832/j.jnpe.2018.S1.0079
[8]	Zhang Liang, Wang Hai, Tong Mingyan, SuN Sheng, Yang Wenhua, Si Junping. Pre-Conceptual Design and Analysis of a SCWR-FQT Loop Test Section Based on CSR1000[J]. Nuclear Power Engineering, 2017, 38(6): 92-98. doi: 10.13832/j.jnpe.2017.06.0092
[9]	ZHANG Jing, ZHAO Shouzhi, GUO Ya, GUO Xiaowei. Conceptual Design of Annular Fuel Element Small Reactor[J]. Nuclear Power Engineering, 2015, 36(6): 1-3. doi: 10.13832/j.jnpe.2015.06.0001
[10]	CHEN Chao, DAN Jianqiang, ZHANG Bo. Sub-Channel Analysis of SCWR Assembly with Double-row Fuel Rods[J]. Nuclear Power Engineering, 2014, 35(2): 27-32.
[11]	LUO Feng, ZHOU Tao, CHENG Wan-xu, SU Zi-wei, CHEN Juan. Sensitivity Analysis for Transient of Partial Loss of Reactor Coolant Flow of Super LWR[J]. Nuclear Power Engineering, 2013, 34(4): 100-105.
[12]	XIA Bangyang, YANG Ping, WANG Lianjie, LI Qing, LI Xiang. Study on Reactivity Control Method for Supercritical Water-Cooled Reactor CSR1000[J]. Nuclear Power Engineering, 2013, 34(1): 26-30.
[13]	XIAO Ze-jun, LI Xiang, HUANG Yan-ping, TANG Rui, LUO Qi, ZANG Feng-gang, LI Qing, LI Peng-zhou, YI Wei. Overview of Research and Development （Phase Ⅰ） on Key Technologies for Supercritical Water-Cooled Reactor[J]. Nuclear Power Engineering, 2013, 34(1): 1-4,14.
[14]	ZENG Xiao-kang, LI Yong-liang, YAN Xiao, XIAO Ze-jun, HUANG Yan-ping. Application of CFD Methods in Research of SCWR Thermo-Hydraulics[J]. Nuclear Power Engineering, 2013, 34(1): 114-120.
[15]	MA Yong-qiang, CHAI Xiao-ming, WANG Yu-wei, PAN Jun-jie, AN Ping. Development of Coupled Neutronics/Thermal-Hydraulics CASIR Code System for SCWR Core Steady State[J]. Nuclear Power Engineering, 2013, 34(1): 87-91.
[16]	AN Ping, WANG Lian-jie, PAN Jun-jie, LU Wei, YAO Dong. Performance Analysis on the Two-Row Hexagonal Fuel Assembly for Super Critical Water-Cooled Reactor[J]. Nuclear Power Engineering, 2013, 34(1): 31-34.
[17]	DU Dai-quan, XIAO Ze-jun, YAN Xiao, CENG Xiao-kang, HUANG Yan-ping. Subchannel Analysis of SCWR CSR1000 Assembly[J]. Nuclear Power Engineering, 2013, 34(1): 40-44.
[18]	SUI Hai-ming, DAN Jian-qiang, HUANG Xue-kong, GOU Jun-li, YANG Hong. Design Scheme of Special Safety System for Supercritical-Water-Cooled Reactor[J]. Nuclear Power Engineering, 2013, 34(1): 71-74.
[19]	SUN Lu, SUN Li-cheng, YAN Chang-qi, FA Dan, ZHAO Xing-bin. Conceptual Design of Passive Residual Heat Removal System for 10 MW Molten Salt Reactor[J]. Nuclear Power Engineering, 2013, 34(6): 107-110.
[20]	XIA Bang-yang, YANG Ping, WANG Lian-jie, MA Yong-qiang, LI Qing, LI Xiang, LIU Jing-bo. Core Preliminary Conceptual Design of Supercritical Water-Cooled Reactor CSR1000[J]. Nuclear Power Engineering, 2013, 34(1): 9-14.