METHOD OF QUALIFICATION OF NUCLEAR AND ENVIRONMENTAL SAFETY SYSTEMS OF NUCLEAR POWER PLANTS WITH VVER-1000 AND AR-1000

Abstract A deterministic method of analyzing the relative criteria and safety conditions of nuclear power plants of various types has been developed. The method is based on comparing the provision of necessary safety functions with critical (minimum permissible) configurations of safety systems for accident management. On the basis of the developed method, the relative safety criteria and conditions of nuclear power plants with reactors of the VVER-1000 and AR-1000 type were determined in relation to the safety functions of the emergency refueling and cooling of the active zone of the reactor of tap generators. On the basis of the established relative criteria and safety conditions, the need for additional upgrades of the AR-1000 safety systems has been pre-determined to successfully ensure the safety functions of emergency refueling of the coolant/feed water and cooling of the active zone of the reactor and steam generators.References: 1. SKALOZUBOV V.Y., KLYUCHNIKOV A.A., KOLYKHANOV V.N. Fundamentals of managing extra-design accidents with loss of coolant at the VVER NPP/ IPB NPP of the Na-tional Academy of Sciences of Ukraine, 400, - 2010 [In Ukraine]. 2. Accident Management Programs in Nuclear Power Plants. Technical Report Series, Vien-na: IAEA, 368, 1994 [In Vienna]. 3. BUKRINSKY A. Development of Deterministic Approach to the Beyond Design Basis Accident Management in Application to NPP units with WWER-1000. SAM-99 Information Ex-change Forum on "Severe Accident Management". Obninsk (Russia), October 18 – 22, 1999 [In Russia]. 4. BEZLEPKIN V.V. ET AL. Severe Accident Management Measures for Tianwan NPP with WWER-1000. OECD Workshop on the Implementation of Severe Accident Management Measures. – Villigen-PSI (Switzerland), September 10 – 13, 2001 [In Switzerland]. 5. ANTROPOV V.N., BUKRINSKY A.M., KUZNETSOV M.V. On the need to develop recommendations for the preparation of a manual for managing extra-design accidents at nuclear power plants. National Nuclear Research Center of Gosatomnadzor of the Russian Federation, 2000 [In Russia]. 6. IAEA-EBP-WWER-05. Safety Issues and Their Ranking for WWER-1000 Model 320 Nuclear Power Plants, 1996 [In Ukraine]. 7. Technical substantiation of security of the Tianvan NPP, 2008 [In Ukraine]. 8. 43-923.203.254.OB.19.03-2003. Khmelnytskyi NPP. Power unit, 2, Part 3. Safety analy-sis report. Quantitative assessment, 2003 [In Ukraine]. 9. 10054 DL13R. Zaporozhye NPP. Power unit. Safety analysis report (OSA), 5, 2000. [In Ukraine]. 10. Security analysis report. 4th unit of Rivne NPP. - SE NAEK "Energoatom". [In Ukraine]. 11. Improvement of VVER fuel safety criteria in LOCA and RIA conditions. Materials of the conference. "Ensuring the safety of nuclear power plants with VVER". Podolsk (Russia): FSUE VNIINM – FSUE OKB "GP", 2008 [In Russia]. 12. BIBILASHVILI YU.K., SOKOLOV N.B., ANDREEVA-ANDRIEVSKAYA L.N. Thermomechanical properties of zirconium-based alloys oxidized claddings in LOCA simulating conditions. Techn. Committee Meeting on Fuel behavior under transient and LOCA conditions, 2001 [In Norway]. 13. SOKOLOV N.B., ANDREEVA-ANDRIEVSKAYA L.N., TONKOV V.YU. Thermo-mechanical properties of irradiated Zr1%Nb alloy claddings in LOCA simulating conditions. JAERI-Conf 2002-2009. Proc. Fuel Safety Research Specialists' Meeting, 200-218, 2002 [In Japan]. 14. SKALOZUBOV V., PIRKOVSKIY D., KOMAROV YU, KOZLOV I. Modeling Method of Conditions for Reliability Critical Hydraulic Impacts on Pumps of Thermal and Nuclear Power Plants. Problems of Atomic Science and Technology, 40 (4), 74 – 79, 2017 [In Ukraine]