Fuel Pin Melting in a Fast Reactor and Melt Solidification: Simulation Using the SAFR/V1 Module of the EVKLID/V2 Integral Code

Author:

Usov E. V.,Butov A. A.,Chukhno V. I.,Klimonov I. A.,Kudashov I. G.,Zhdanov V. S.,Pribaturin N. A.,Mosunova N. A.,Strizhov V. F.

Publisher

Springer Science and Business Media LLC

Subject

Nuclear Energy and Engineering

Reference12 articles.

1. V. M. Alipchenkov, V. V. Belikov, V. N. Vasekin, et al., “Verification of the integrated universal constitutional code EVKLID/V1 in application to the installations BREST-OD-300 and BN-1200,” in: Innovative Projects and Technologies of Nuclear Power, Moscow, Oct. 7–10, 2014, Vol. 2, pp. 175–191.

2. A. A. Butov, E. V. Usov, V. S. Zhdanov, et al., “SAFR module of the integrated code EVKLID/V2 or calculator problems with melting of fast reactor fuel pins,” in: Abstr. Sci. Techn. Conf. on Thermophysics of Next-Generation Reactors, Thermophysics-2016, Obninsk, Oct. 12–14, 2016, pp. 165–166.

3. A. A. Kalashnikova and E. V. Usov, “Development of a software module for calculating the melting of fuel pins and movement of melt in fast-neutron reactor installations during a serious accident,” in: Russ. Youth Conf. on Power Generation, Electromechanics, and Energy-Efficient Technologies in the Eyes of Youth, Izd. SKAN, Tomsk (2015), pp. 135–138.

4. V. Alexiades and A. D. Solomon, Mathematical Modeling of Melting and Freezing Processes, Hemisphere Publ. Co, Washington (1993).

5. S. K. Godunov and V. S. Ryaben’kii, Difference Schemes. Nauka, Moscow (1973).

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