Issue |
EPJ Nuclear Sci. Technol.
Volume 9, 2023
Euratom Research and Training in 2022: the Awards collection
|
|
---|---|---|
Article Number | 4 | |
Number of page(s) | 9 | |
Section | Part 1: Safety research and training of reactor systems | |
DOI | https://doi.org/10.1051/epjn/2022047 | |
Published online | 10 January 2023 |
- H. Aït Abderrahim, D. De Bruyn, G. Van den Eynde, S. Michiels, Transmutation of high-level nuclear waste by means of accelerator driven system, Wiley Interdiscip. Rev. Energy Environ. 3, 60–69 (2014) [Google Scholar]
- M. Salvatores, G. Palmiotti, Radioactive waste partitioning and transmutation within advanced fuel cycles: Achievements and challenges, Prog. Part. Nucl. Phys. 66, 144–166 (2011) [CrossRef] [Google Scholar]
- A.E. Waltar, D.R. Todd, P.V. Tsvetkov, Fast Spectrum Reactors (Springer, New York, 2012) [CrossRef] [Google Scholar]
- H.H. Hummel, D. Okrent, Reactivity Coefficients in Large Fast Power Reactors (American Nuclear Society, Illinois, 1970) [Google Scholar]
- H.A. Bethe, J.H. Tait, An estimate of the order of magnitude of the explosion when the core of a fast reactor collapses, UKAEA-RHM 56, 113 (1956) [Google Scholar]
- Working Party on Scientific Issues of the Fuel Cycle, Working Group on Lead-bismuth Eutectic, Tech. Rep., OECD/NEA Nuclear Science Committee, 2007 [Google Scholar]
- B. Arien, S. Heusdains, H. Aït Abderrahim, E. Malambu, Safety Analysis of the MYRRHA Facility with Different Core Configurations, in Proceedings of the PHYSOR-2006 Conference, ANS Topical Meeting on Reactor Physics, Vancouver, Canada, September 10–14 (2006) [Google Scholar]
- S. Kondo, Y. Tobita, K. Morita, N. Shirakawa, SIMMER-III: An Advanced Computer Program for LMFBR Severe Accident Analysis, in Proceedings of the International Conference on Design and Safety of Advanced Nuclear Power Plants, Tokyo, Japan, October 25–29 (1992) [Google Scholar]
- W. Maschek, A. Rineiski, M. Flad, P. Liu, X.N. Chen, Y. Tobita, H. Yamano, T. Suzuki, S. Fujita, K. Kamiyama, S. Pigny, T. Cadiou, K. Morita, G. Bandini, The SIMMER safety code system and its validation efforts for fast reactor application, in Proceedings of the PHYSOR-2008 Conference, Interlaken, Switzerland, September 14–19 (2008) [Google Scholar]
- J. Leppänen, M. Pusa, T. Viitanen, V. Valtavirta, T. Kaltiaisenaho, The serpent Monte Carlo Code: Status, development and applications in 2013, Ann. Nucl. Energy 82, 142–150 (2015) [CrossRef] [Google Scholar]
- K.O. Ott, R.J. Neuhold, Introductory Nuclear Reactor Dynamics (American Nuclear Society, Illinois, 1985) [Google Scholar]
- J.H. Lienhard IV, J.H. Lienhard V, A Heat Transfer Textbook (Phlogiston Press, Boston, 2011) [Google Scholar]
- R. Coulson, MSc Thesis, Colorado School of Mines, Faculty of Engineering, 2013, p. 14. [Google Scholar]
- N.E. Todreas, M.S. Kazimi, Nuclear Systems I: Thermal Hydraulic Fundamentals (Taylor and Francis, Boston, 1993) [Google Scholar]
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