Potential model for Modified Embedded Atom Method on Pu-Fe alloy system has been developed to analyze the metal reaction between Pu and Fe with classical molecular dynamics in the framework of the development of the new MPS-based code named ‘COMPASS’ [1] for meso-scale analysis of core disruptive accidents in Sodium-cooled fast reactor. The parameters on Pu-Fe interaction were determined so as to reproduce the properties of PuFe2 intermetallic compound, with applying the potential model for the individual components of Pu and Fe proposed in previous studies. First principle calculations were preformed to compensate for the available experimental data on the material properties of PuFe2. The developed model well reproduces the properties of PuFe2. In the simulation in which the solid Fe is in contact with liquid or solid Pu, formation of crystalline structure of Pu atoms mimicking the Fe structure is observed near the Pu-Fe interface.
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17th International Conference on Nuclear Engineering
July 12–16, 2009
Brussels, Belgium
Conference Sponsors:
- Nuclear Engineering Division
ISBN:
978-0-7918-4355-0
PROCEEDINGS PAPER
Next Generation Safety Analysis Methods for SFRs—(7) Potential Model for Classical Molecular Dynamics on Pu-Fe System Available to Purchase
Takahiro Ito,
Takahiro Ito
Toyohashi University of Technology, Toyohashi, Japan
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Tatsumi Arima,
Tatsumi Arima
Kyushu University, Fukuoka, Japan
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Masashi Himi
Masashi Himi
Japan Systems Corporation, Kawasaki, Kanagawa, Japan
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Takahiro Ito
Toyohashi University of Technology, Toyohashi, Japan
Tatsumi Arima
Kyushu University, Fukuoka, Japan
Masashi Himi
Japan Systems Corporation, Kawasaki, Kanagawa, Japan
Paper No:
ICONE17-75591, pp. 525-533; 9 pages
Published Online:
February 25, 2010
Citation
Ito, T, Arima, T, & Himi, M. "Next Generation Safety Analysis Methods for SFRs—(7) Potential Model for Classical Molecular Dynamics on Pu-Fe System." Proceedings of the 17th International Conference on Nuclear Engineering. Volume 5: Fuel Cycle and High and Low Level Waste Management and Decommissioning; Computational Fluid Dynamics (CFD), Neutronics Methods and Coupled Codes; Instrumentation and Control. Brussels, Belgium. July 12–16, 2009. pp. 525-533. ASME. https://doi.org/10.1115/ICONE17-75591
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