Method of Analysis of Thermophysical Properties and Composition of Nuclear Fuel During Modernization of Active Zones of Nuclear Power Reactors

• Autorzy: Vashchenko Volodymyr , Skalozubov Volodymyr , Korduba Iryna , Komarov Yuriy , Zhukova Olena

Identyfikatory

DOI

10.12912/27197050/168372

• Języki publikacji: EN

Abstrakty

EN

The developed alternative method of analyzing the safety of the active zone of reactor installations is justified for improving the thermophysical properties and composition of nuclear fuel, designs of heat-releasing assemblies, reactor operation modes at increased or reduced power, etc. The impact of modernization on the safety criteria and conditions of reactor installations (RF) was analyzed. Attention was focused on the fact that until now there have been no sufficiently substantiated and accepted criteria and conditions for "steam" explosions in the Russian Federation. It was shown that when analyzing the safety of HF modernization with deterministic codes, it is necessary to take into account the possibility of negative effects of "user code" (EUC) and "code difference" (ECD), which can significantly affect the results of re-simulation of accidents with deterministic codes taking into account modernizations.

Słowa kluczowe

EN

safety analysis; reactor facility; RF; upgrade; steam explosion; deterministic code; user code effect; code difference effect

• Wydawca: Lubelski Oddział Polskiego Towarzystwo Inżynierii Ekologicznej ; Lublin University of Technology ; WNGB Wydawnictwo Naukowe
• Czasopismo: Ecological Engineering & Environmental Technology
• Rocznik: 2023
• Tom: Vol. 24, iss. 6
• Strony: 186--191
• Opis fizyczny: Bibliogr. 9 poz., rys.

Twórcy

autor

Vashchenko Volodymyr

• Department of Ecology, National Aviation University, 1, Huzara Lyubomyra Ave., Kyiv, 03058, Ukraine

• https://orcid.org/0000-0003-1585-2129

autor

Skalozubov Volodymyr

• Interdepartmental Center for Fundamental Scientific Research in the Field of Energy and Ecology of the National Academy of Sciences of Ukraine, “Odessa Polytechnic” and the Ministry of Ecology of Ukraine, 1, Shevchenko Ave, Odesa, 65044, Ukraine

• https://orcid.org/0000-0003-2361-223X

autor

Korduba Iryna

• Department of Environmental Protection and Labor Protection Technology, Kyiv National University of Construction and Architecture, 31, Povitroflotskyi Ave., Kyiv, 03037, Ukraine

• https://orcid.org/0000-0001-5135-8465

autor

Komarov Yuriy

• Interdepartmental Center for Fundamental Scientific Research in the Field of Energy and Ecology of the National Academy of Sciences of Ukraine, “Odessa Polytechnic” and the Ministry of Ecology of Ukraine, 1, Shevchenko Ave, Odesa, 65044, Ukraine

• https://orcid.org/0000-0002-4696-6551

autor

Zhukova Olena

• Department of Environmental Protection and Labor Protection Technology, Kyiv National University of Construction and Architecture, 31, Povitroflotskyi Ave., Kyiv, 03037, Ukraine

• https://orcid.org/0000-0003-0662-9996

Bibliografia

• 1. Vasylchenko V.N., Emelyanenko E.Z., Skalozubov V.I. 2002. Modeling of accidents at nuclear power plants of nuclear power plants. Odessa, Rezon.
• 2. Security analysis report. Block 5. Zaporizhia NPP. Final report. 2002. Energodar: SE NAEK “Energoatom”.
• 3. Western European practice of verification and validation of calculation codes. 1997. Report on the TACIS program UK/TS/09.
• 4. Kim V.V., Skalozubov V.I. 1999. On the issue of regulating the applicability of software tools in the analysis of accidents at domestic reactors. Nuclear and radiation safety, 1, 45–51.
• 5. Analysis of experimental data with the results of computational studies of dynamic modes of operation of VVER-1000 power units. 1991. Questions of atomic science and technology. Ser. Physics and technology of nuclear reactors, 17.
• 6. Podlazov L.N., Trekhov V.E., Cherkashov Yu.M. 1994. Computational modeling of the accident at the fourth unit of the Chernobyl NPP. Atomic Energy, 77(2), 9–15.
• 7. Skalozubov V.Y., Emelyanenko E.Z., Kim V.V. 1999. Analysis of the similarity of thermohydrodynamic processes in the circulation circuit at fullscale installations and integral experimental stands. Nuclear and radiation safety, 2(3), 45–55.
• 8. IAEA-TECDOC-848-1995. Simulation of a loss of coolant accident without high pressure injection but with secondary side bleed and feed. Results of the fourth standard problem exercise on the simulation of loss of coolant accidents. Report of the IAEA. Technical Co-operation Project Aspects of WWER-440 Model 213 NPP.
• 9. Skalozubov V.Y., Vasylchenko V.N., Kim V.V., Emelyanenko E.Z. 1999. Analysis of the similarity of thermohydrodynamic processes in the active zone of full-scale installations and integral experimental stands. Nuclear and radiation safety, 2(1), 69–76.