This paper studies the KBS-3 spent fuel canister criticality safety issue in the event of a groundwater penetration accident. First, the study calculates the composition of the PWR spent fuel assemblies by using MCBURN software, and the coupling of the MCNP and ORIGEN 2.1 computer codes. Then, with the help of Isotope Generation and Depletion Code, it calculates the composition of various types of actinides and their daughters for 100,000 years. Finally, the above calculation results are used in MCNP5 to calculate the effective multiplication factor keff of the canister for different degrees of groundwater penetration. The study finds that the maximum keff of the canister is 0.79609 in groundwater penetration accident, satisfying criticality safety standard.
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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
Spent Fuel Canister Criticality Safety Calculation in Groundwater Immersion Accident Available to Purchase
Siyuan Wu,
Siyuan Wu
East China Institute of Technology, Nanchang, JiangXi, China
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Bo Yang,
Bo Yang
East China Institute of Technology, Nanchang, JiangXi, China
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Hexi Wu,
Hexi Wu
East China Institute of Technology, Nanchang, JiangXi, China
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Qianglin Wei,
Qianglin Wei
East China Institute of Technology, Nanchang, JiangXi, China
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Yibao Liu
Yibao Liu
East China Institute of Technology, Nanchang, JiangXi, China
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Siyuan Wu
East China Institute of Technology, Nanchang, JiangXi, China
Bo Yang
East China Institute of Technology, Nanchang, JiangXi, China
Hexi Wu
East China Institute of Technology, Nanchang, JiangXi, China
Qianglin Wei
East China Institute of Technology, Nanchang, JiangXi, China
Yibao Liu
East China Institute of Technology, Nanchang, JiangXi, China
Paper No:
ICONE22-30978, V004T08A016; 4 pages
Published Online:
November 17, 2014
Citation
Wu, S, Yang, B, Wu, H, Wei, Q, & Liu, Y. "Spent Fuel Canister Criticality Safety Calculation in Groundwater Immersion Accident." 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. V004T08A016. ASME. https://doi.org/10.1115/ICONE22-30978
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