Development of multi-group Monte-Carlo transport and depletion coupling calculation method and verification with metal-fueled fast reactor
Author:
Publisher
Springer Science and Business Media LLC
Subject
Nuclear Energy and Engineering,Nuclear and High Energy Physics
Link
https://link.springer.com/content/pdf/10.1007/s41365-023-01310-3.pdf
Reference37 articles.
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3. D.P. Griesheimer, D.F. Gill, B.R. Nease et al., MC21 v.6.0 – A Continuous-Energy Monte Carlo Particle Transport Code with Integrated Reactor Feedback Capabilities, in: SNA MC 2013 - Jt. Int. Conf. Supercomput. Nucl. Appl. Monte Carlo, EDP Sciences, 2014: p. 06008. https://doi.org/10.1051/snamc/20140600
4. J. Leppänen, M. Pusa, T. Viitanen et al., The Serpent Monte Carlo code: status, development and applications in 2013. Ann. Nucl. Energy 82, 142–150 (2015). https://doi.org/10.1016/j.anucene.2014.08.024
5. L. Deng, G. Li, B.-Y. Zhang et al., A high fidelity general purpose 3-D Monte Carlo particle transport program JMCT3.0. Nucl. Sci. Tech. 33, 108 (2022). https://doi.org/10.1007/s41365-022-01092-0
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