Early phase behavior of steam line break accidents in the VVER-1200 reactor: Effect of break location, AC power loss, and break size
Öz
This study investigates the early-phase (0–300 s) behavior of steam line break (SLB) accidents in a VVER-1200 pressurized water reactor, with and without AC power availability, using the PCTRAN simulation code. Break location and power supply status are treated as the primary governing parameters. Eight comparative accident scenarios are developed to represent different break configurations. Reactor building pressure and peak fuel cladding temperature (PCT), which are critical safety indicators, are evaluated as time-dependent responses. The results demonstrate that break location and AC power availability exert the dominant influence on containment pressure evolution. SLB events occurring inside the reactor building lead to pronounced pressure increases, particularly under AC power-loss conditions, whereas breaks outside the building maintain pressure close to atmospheric levels. Across all investigated scenarios, peak fuel cladding temperatures remain below safety limits, indicating that natural circulation and passive safety systems effectively sustain core cooling even during power loss. Overall, the findings confirm the high early-phase safety margin of the VVER-1200 design against SLB accidents and highlight the decisive role of system configuration in transient safety assessment.
Anahtar Kelimeler
Kaynakça
- [1] Nath PD, Rahman KM, Bari MAA. Thermal hydraulic analysis of a nuclear reactor due to loss of coolant accident with and without emergency core cooling system. Journal of Engineering Advancements 2020; 1(2): 53–60.
- [2] Sofrany EA, Widodo S. Analysis of steam generator tube rupture (SGTR) based on Mihama Unit 2 scenario; Analisis kejadian steam generator tube rupture (SGTR) berdasarkan skenario Mihama Unit 2. Indonesia, 2010.
- [3] Saleh W, Kim J. Assessment of source terms and potential doses due to steam generator tube rupture of VVER-1200 at the El Dabaa nuclear power plant in Egypt. Journal of Radiation Protection and Research 2025; 50(S1): S30–S42.
- [4] Mondal, J, Afsar SM Anan. Analysis of Nuclear Reactor Parameters in the VVER-1200 during a Loss of Coolant Accident and Steam Generator Tube Rupture with Emergency Core Cooling System Failure. SciEn Conference Series: Engineering 2025; Vol. 3.
- [5] Chenshi Y, Yaru L. Analysis and research on long-term safety and stability state of VVER-1200 after FLB accident. Proceedings of the 32nd International Conference on Nuclear Engineering (ICONE 2025) Weihai, China, 2025.
- [6] Bagheri, AA, Zohuri, B. Study on Severe Accidents of the New Generation WWER-1200 Reactor. Journal of Material Sciences & Manufacturing Research 2022; (3), 134.
- [7] Khan AH, Ghosh AK, Rahman MS, Ahmed SMT, Karmaker CL. Investigation of possible radioactive contamination of environment during a steam-line break accident in a VVER-1200 nuclear power plant. Current World Environment 2019; 14(2): 299–311.
- [8] Fyza N, Hossain A, Sarkar R. Analysis of thermal-hydraulic parameters of VVER-1200 due to loss of coolant accident concurrent with loss of offsite power. Energy Procedia 2019; 160: 155–161.
Ayrıntılar
Birincil Dil
İngilizce
Konular
Enerji, Nükleer Enerji Sistemleri
Bölüm
Araştırma Makalesi
Yazarlar
Güven Tunç
*
0000-0001-7038-8168
Türkiye
Tuna Han Ulu
0009-0002-6761-9193
Türkiye
Ömer Faruk Yılmaz
0009-0007-7166-7848
Türkiye
Yayımlanma Tarihi
17 Mart 2026
Gönderilme Tarihi
1 Şubat 2026
Kabul Tarihi
25 Şubat 2026
Yayımlandığı Sayı
Yıl 2026 Cilt: 11 Sayı: 1