Design options of large scale sodium cooled fast reactors are being studied intensively in China, and China Fast Reactor 1000 (CFR-1000) is one of the options. An unprotected transient overpower (UTOP) scenario analysis is carried out during the concept design phase of CFR-1000, aiming at estimating the safety performances of the core during the transient and providing feedbacks for the design. Reactivity insertion scenarios are simulated with different reactivity insertion rates. Safety aspects of core design are evaluated based on the simulation and analyses, including the design of reactivity feedbacks, the design of control rod as well as safety margin of fuel and cladding. The UTOP scenario analysis provides insights of CFR-1000 core design in safety aspect, and valuable information on safety design is given for future China fast reactor design.
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2013 21st International Conference on Nuclear Engineering
July 29–August 2, 2013
Chengdu, China
Conference Sponsors:
- Nuclear Engineering Division
ISBN:
978-0-7918-5579-9
PROCEEDINGS PAPER
Safety Performance of a Large Scale Sodium Cooled Fast Reactor in Unprotected Transient Overpower Scenarios
Yuanyu Wu,
Yuanyu Wu
China Institute of Atomic Energy, Beijing, China
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Hong Yu,
Hong Yu
China Institute of Atomic Energy, Beijing, China
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Lixia Ren,
Lixia Ren
China Institute of Atomic Energy, Beijing, China
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Wenjun Hu
Wenjun Hu
China Institute of Atomic Energy, Beijing, China
Search for other works by this author on:
Yuanyu Wu
China Institute of Atomic Energy, Beijing, China
Hong Yu
China Institute of Atomic Energy, Beijing, China
Lixia Ren
China Institute of Atomic Energy, Beijing, China
Wenjun Hu
China Institute of Atomic Energy, Beijing, China
Paper No:
ICONE21-16704, V002T05A068; 5 pages
Published Online:
February 7, 2014
Citation
Wu, Y, Yu, H, Ren, L, & Hu, W. "Safety Performance of a Large Scale Sodium Cooled Fast Reactor in Unprotected Transient Overpower Scenarios." Proceedings of the 2013 21st International Conference on Nuclear Engineering. Volume 2: Plant Systems, Construction, Structures and Components; Next Generation Reactors and Advanced Reactors. Chengdu, China. July 29–August 2, 2013. V002T05A068. ASME. https://doi.org/10.1115/ICONE21-16704
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