The EUCLID/V1 Integrated Code for Safety Assessment of Liquid Metal Cooled Fast Reactors. Part 1: Basic Models
Author:
Publisher
Pleiades Publishing Ltd
Subject
Energy Engineering and Power Technology,Nuclear Energy and Engineering
Link
http://link.springer.com/content/pdf/10.1134/S0040601518050063.pdf
Reference56 articles.
1. The White Book of Nuclear Power Generation Ed. by E. O. Adamov, (NIKIET, Moscow, 2001) [in Russian].
2. P. N. Alekseev, V. G. Asmolov, A. Yu. Gagarinskii, N. E. Kukharkin, Yu. M. Semchenkov, V. A. Sidorenko, S. A. Subbotin, V. F. Tsibul’skii, and Ya. I. Shtrombakh, “On a nuclear power strategy of Russia to 2050,” At. Energy 111, 239–251 (2011).
3. L. A. Bol’shov, N. A. Mosunova, V. F. Strizhov, and O. V. Shmidt, “Next generation design codes for a new technological platform for nuclear power,” At. Energy 120, 369–379 (2016).
4. I. G. Kudashov, E. V. Usov, A. A. Butov, I. S. Vozhakov, N. A. Pribaturin, S. I. Lezhnin, M. E. Kuznetsova, Yu. Yu. Vinogradova, R. V. Chalyi, V. N. Semenov, A. L. Fokin, and N. I. Ryzhov, “Heat-exchange models in the SOKRAT-BN Code for calculating sodium boiling in geometrically different channels,” At. Energy 117, 323–328 (2014).
5. T. Suzuki, Y. Tobita, K. Kawada, H. Tagami, J. Sogabe, K. Matsuba, K. Ito, and H. Ohshima, “A preliminary evaluation of unprotected loss-of-flow accident for a prototype fast-breeder reactor,” Nucl. Eng. Technol. 47, 240–252 (2015).
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