Simulation of Melt Behavior in the Sodium-Cooled Reactor Core Catcher Using the EUCLID/V2 Integrated Computer Code HEFEST-FR Module

Author:

Butov A. A.,Kamenskaya D. D.,Klimonov I. A.,Mosunova N. A.,Usov E. V.,Tsaun S. V.,Chukhno V. I.

Publisher

Pleiades Publishing Ltd

Subject

Energy Engineering and Power Technology,Nuclear Energy and Engineering

Reference29 articles.

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2. O. L. Tashlykov, Fundamentals of Nuclear Energy: Tutorial (Ural. Fed. Univ., Yekaterinburg, 2016) [in Russian].

3. I. A. Kuznetsov and V. M. Poplavskii, Safety of Nuclear Power Plants with Fast Neutron Reactors (IzdAt, Moscow, 2012) [in Russian].

4. Yu. G. Dragunov, V. V. Lemekhov, A. V. Moiseev, V. S. Smirnov, O. A. Yarmolenko, V. P. Vasyukhno, and Yu. S. Cherepnin, “Technical project RU BREST-OD-300: Stages of development and substantiation,” in Innovational Projects and Technologies of Nuclear Power Industry: Proc. 4th Int. Sci. and Tech. Conf., Moscow, Russia, Sept. 27–30, 2016 (NIKIET, Moscow, 2016), Vol. 1, pp. 21–30.

5. E. O. Adamov, “Closed fuel cycle technologies based on fast reactors as the corner stone for sustainable development of nuclear power,” in Fast Reactors and Related Fuel Cycles: Next Generation Nuclear Systems for Sustainable Development (FR17): Proc. Int. Conf., Yekaterinburg, Russia, June 26–29, 2017 (International Atomic Energy Agency, 2017), paper no. IAEA-CN245-342.

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