In order to enhance the efficiency and obtain more safety margin in the new type nuclear power plant design, it is of great necessity and significance to study the potential probability of vessel structure design improvement which is based on CPR1000 NP. In this paper, LB LOCA is chosen as the typical accident with CATHARE GB code and the DRM applied. Sensitivity study of in-vessel structure, length of fuel rods and the water inventory are performed. The result shows that by reducing the length between the vessel bottom and the core inlet, extending the fuel rod length and increasing primary water inventory, the PCT declines respectively. More than 200 K temperature benefit can be obtained when the three modifications mentioned above combined together. Due to the sufficient margin increased, a proper power uprating is feasible.
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2013 21st International Conference on Nuclear Engineering
July 29–August 2, 2013
Chengdu, China
Conference Sponsors:
- Nuclear Engineering Division
ISBN:
978-0-7918-5580-5
PROCEEDINGS PAPER
Preliminary Study on the Primary Side Structure Design Improvement Based on CPR1000
Jianshu Lin
,
Jianshu Lin
China Nuclear Power Technology Research Institute, Shenzhen, Guangdong, China
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Chengjun Zhuang
,
Chengjun Zhuang
China Nuclear Power Technology Research Institute, Shenzhen, Guangdong, China
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Jun Cui
,
Jun Cui
China Nuclear Power Technology Research Institute, Shenzhen, Guangdong, China
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Ting Wang
,
Ting Wang
China Nuclear Power Technology Research Institute, Shenzhen, Guangdong, China
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Zhenhua Zhang
Zhenhua Zhang
China Nuclear Power Technology Research Institute, Shenzhen, Guangdong, China
Search for other works by this author on:
Jianshu Lin
China Nuclear Power Technology Research Institute, Shenzhen, Guangdong, China
Chengjun Zhuang
China Nuclear Power Technology Research Institute, Shenzhen, Guangdong, China
Jun Cui
China Nuclear Power Technology Research Institute, Shenzhen, Guangdong, China
Ting Wang
China Nuclear Power Technology Research Institute, Shenzhen, Guangdong, China
Zhenhua Zhang
China Nuclear Power Technology Research Institute, Shenzhen, Guangdong, China
Paper No:
ICONE21-15687, V003T06A022; 7 pages
Published Online:
February 7, 2014
Citation
Lin, J, Zhuang, C, Cui, J, Wang, T, & Zhang, Z. "Preliminary Study on the Primary Side Structure Design Improvement Based on CPR1000." Proceedings of the 2013 21st International Conference on Nuclear Engineering. Volume 3: Nuclear Safety and Security; Codes, Standards, Licensing and Regulatory Issues; Computational Fluid Dynamics and Coupled Codes. Chengdu, China. July 29–August 2, 2013. V003T06A022. ASME. https://doi.org/10.1115/ICONE21-15687
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