A space-time nodal transport code, DAISY, was developed to evaluate dynamic neutron behavior in innovative nuclear system. The steady transport process is based on an arbitrary triangles-z mesh nodal method which can treat complicated geometry configuration with enough precision and acceptable calculated quantity. This code employs the improved quasi-static method for neutron kinetics with a predictor-corrector scheme to improve computational efficiency. The direct method and the point approximation for neutron kinetics are also implemented into DAISY to evaluate the precision and efficiency of this predictor-corrector scheme. This code was verified by several transient benchmarks. It shows that the predictor-corrector scheme in DAISY can greatly reduce the computational time with enough precision.
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2014 22nd International Conference on Nuclear Engineering
July 7–11, 2014
Prague, Czech Republic
Conference Sponsors:
- Nuclear Engineering Division
ISBN:
978-0-7918-4594-3
PROCEEDINGS PAPER
Time-Dependent, Three Dimensional Nodal Transport Code Development Based on Unstructured Mesh Available to Purchase
Mingtao He,
Mingtao He
Xi’an Jiaotong University, Xi’an, Shaanxi, China
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Hongchun Wu,
Hongchun Wu
Xi’an Jiaotong University, Xi’an, Shaanxi, China
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Liangzhi Cao,
Liangzhi Cao
Xi’an Jiaotong University, Xi’an, Shaanxi, China
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Youqi Zheng,
Youqi Zheng
Xi’an Jiaotong University, Xi’an, Shaanxi, China
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ShengCheng Zhou
ShengCheng Zhou
Xi’an Jiaotong University, Xi’an, Shaanxi, China
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Mingtao He
Xi’an Jiaotong University, Xi’an, Shaanxi, China
Hongchun Wu
Xi’an Jiaotong University, Xi’an, Shaanxi, China
Liangzhi Cao
Xi’an Jiaotong University, Xi’an, Shaanxi, China
Youqi Zheng
Xi’an Jiaotong University, Xi’an, Shaanxi, China
ShengCheng Zhou
Xi’an Jiaotong University, Xi’an, Shaanxi, China
Paper No:
ICONE22-31018, V004T11A014; 8 pages
Published Online:
November 17, 2014
Citation
He, M, Wu, H, Cao, L, Zheng, Y, & Zhou, S. "Time-Dependent, Three Dimensional Nodal Transport Code Development Based on Unstructured Mesh." Proceedings of the 2014 22nd International Conference on Nuclear Engineering. Volume 4: Radiation Protection and Nuclear Technology Applications; Fuel Cycle, Radioactive Waste Management and Decommissioning; Computational Fluid Dynamics (CFD) and Coupled Codes; Reactor Physics and Transport Theory. Prague, Czech Republic. July 7–11, 2014. V004T11A014. ASME. https://doi.org/10.1115/ICONE22-31018
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