Fully ceramic micro-encapsulated (FCM) fuels generate double heterogeneity (DH) challenging greatly for classical resonance self-shielding calculation method. New methodologies have been proposed and verified in this research. The target of this study is to provide homogeneous multi-group cross sections reflecting the effect of DH. Embedded Self-Shielding Method (ESSM) [1] was selected to perform resonance self-shielding calculation. Therefore, Monte Carlo code MVP [2] which is capable of well modeling the stochastic dispersed tri-structural isotropic (TRISO) coated fuel particle throughout carbide matrix and method of characteristics (MOC) were chosen to develop the heterogeneous resonance integral (RI) tables for DH problems. Benchmark problems from reference [3] were provided to verify the new methodologies. The results show that ESSM with RI tables from MVP and MOC could well address the resonance calculation for DH problems.
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2017 25th International Conference on Nuclear Engineering
July 2–6, 2017
Shanghai, China
Conference Sponsors:
- Nuclear Engineering Division
ISBN:
978-0-7918-5781-6
PROCEEDINGS PAPER
Resonance Self-Shielding Treatment for Fully Ceramic Micro-Encapsulated Fuels With the Embedded Self-Shielding Method
Jikui Li,
Jikui Li
Xi’an Jiaotong University, Xi’an, China
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Liangzhi Cao,
Liangzhi Cao
Xi’an Jiaotong University, Xi’an, China
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Tiejun Zu,
Tiejun Zu
Xi’an Jiaotong University, Xi’an, China
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HongChun Wu,
HongChun Wu
Xi’an Jiaotong University, Xi’an, China
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Qingming He
Qingming He
Xi’an Jiaotong University, Xi’an, China
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Jikui Li
Xi’an Jiaotong University, Xi’an, China
Liangzhi Cao
Xi’an Jiaotong University, Xi’an, China
Tiejun Zu
Xi’an Jiaotong University, Xi’an, China
HongChun Wu
Xi’an Jiaotong University, Xi’an, China
Qingming He
Xi’an Jiaotong University, Xi’an, China
Paper No:
ICONE25-66810, V003T02A030; 6 pages
Published Online:
October 17, 2017
Citation
Li, J, Cao, L, Zu, T, Wu, H, & He, Q. "Resonance Self-Shielding Treatment for Fully Ceramic Micro-Encapsulated Fuels With the Embedded Self-Shielding Method." Proceedings of the 2017 25th International Conference on Nuclear Engineering. Volume 3: Nuclear Fuel and Material, Reactor Physics and Transport Theory; Innovative Nuclear Power Plant Design and New Technology Application. Shanghai, China. July 2–6, 2017. V003T02A030. ASME. https://doi.org/10.1115/ICONE25-66810
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