Nuclear heating reactor is a new type of power plant that uses nuclear energy as heat source. Low temperature nuclear heating reactor should be the forerunner and main force for developing nuclear heating plant in China. Due to the lower water temperature required by the heating system, this dedicated, non-power generating nuclear reactor works at low temperatures and pressures with inherent safety features. The design, construction and operation of the nuclear heating reactors in various countries in the world were reviewed in this paper, and China’s new demonstration nuclear heating project and NHR-200 low-temperature heating reactor which would be used was discussed in the paper. We put forward the developing route and suggestion for the development of low-temperature heating reactor in China.
Skip Nav Destination
2018 26th International Conference on Nuclear Engineering
July 22–26, 2018
London, England
Conference Sponsors:
- Nuclear Engineering Division
ISBN:
978-0-7918-5143-2
PROCEEDINGS PAPER
Status of District Heating Reactor and its Development Prospects in China Available to Purchase
Zhihong Liu
Zhihong Liu
Tsinghua University, Beijing, China
Search for other works by this author on:
Jing Zhao
Tsinghua University, Beijing, China
Fei Xie
Tsinghua University, Beijing, China
Zhihong Liu
Tsinghua University, Beijing, China
Paper No:
ICONE26-82445, V001T13A024; 4 pages
Published Online:
October 24, 2018
Citation
Zhao, J, Xie, F, & Liu, Z. "Status of District Heating Reactor and its Development Prospects in China." Proceedings of the 2018 26th International Conference on Nuclear Engineering. London, England. July 22–26, 2018. V001T13A024. ASME. https://doi.org/10.1115/ICONE26-82445
Download citation file:
39
Views
Related Proceedings Papers
Related Articles
Current Status of Reactors Deployment and Small Modular Reactors Development in the World
ASME J of Nuclear Rad Sci (October,2020)
Nuclear Fission, Today and Tomorrow: From Renaissance to Technological Breakthrough (Generation IV)
J. Pressure Vessel Technol (August,2011)
Editorial
ASME J of Nuclear Rad Sci (January,2015)
Related Chapters
Threshold Functions
Closed-Cycle Gas Turbines: Operating Experience and Future Potential
Tendon End Anchor Testing
Commentary on Articles CC-2000, CC-3000 and CC-4000
Introduction
Nuclear Reactor Thermal-Hydraulics: Past, Present and Future