Transient computing scheme named K-MOD has been designed that time-discrete is carried out by implicit Runge-Kutta method, and coarse nodal method is used for neutronics calculation at present. During transient calculation, thermal feedback is introduced to update the cross-section to approximate the transient behavior of the real core based on the method of interpolation on state-points. Corresponding thermal feedback for coupling calculation is programmed and analyzed, and parallel computing is introduced to enhance efficiencies of single-disciplinary codes and data coupling section. Problem of rod insertion and lift in real core of PWR (Pressurized Water Reactor) is tested and compared. The results show that K-MOD is in good agreement with the results of SMART software in both fixed time step and adaptive time step. And the parallel efficiency is also explained.
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2018 26th International Conference on Nuclear Engineering
July 22–26, 2018
London, England
Conference Sponsors:
- Nuclear Engineering Division
ISBN:
978-0-7918-5148-7
PROCEEDINGS PAPER
Analysis and Parallel Implementation of Transient Thermal Feedback in Neutron Kinetics Calculation
Pingzhou Ming,
Pingzhou Ming
Nuclear Power Institute of China, Chengdu, China
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Zhigang Li,
Zhigang Li
Nuclear Power Institute of China, Chengdu, China
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Ping An,
Ping An
Nuclear Power Institute of China, Chengdu, China
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Wei Lu,
Wei Lu
Nuclear Power Institute of China, Chengdu, China
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Dong Liu,
Dong Liu
Nuclear Power Institute of China, Chengdu, China
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Hongxing Yu
Hongxing Yu
Nuclear Power Institute of China, Chengdu, China
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Pingzhou Ming
Nuclear Power Institute of China, Chengdu, China
Zhigang Li
Nuclear Power Institute of China, Chengdu, China
Ping An
Nuclear Power Institute of China, Chengdu, China
Wei Lu
Nuclear Power Institute of China, Chengdu, China
Dong Liu
Nuclear Power Institute of China, Chengdu, China
Hongxing Yu
Nuclear Power Institute of China, Chengdu, China
Paper No:
ICONE26-81442, V06AT08A039; 7 pages
Published Online:
October 24, 2018
Citation
Ming, P, Li, Z, An, P, Lu, W, Liu, D, & Yu, H. "Analysis and Parallel Implementation of Transient Thermal Feedback in Neutron Kinetics Calculation." Proceedings of the 2018 26th International Conference on Nuclear Engineering. Volume 6A: Thermal-Hydraulics and Safety Analyses. London, England. July 22–26, 2018. V06AT08A039. ASME. https://doi.org/10.1115/ICONE26-81442
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