Methods of critical heat flux prediction in subcooled water flow in VVER-1200 fuel rods; Научная инициатива иностранных студентов и аспирантов

समान संसाधन

• Features of thermal-hydraulic calculation of subcooled water reactor VVER-1200; Перспективы развития фундаментальных наук; Т. 1 : Физика
  द्वारा: Odii C. J.
  प्रकाशित: (2023)
• Effect of power excursion on the thermal characteristics of VVER-1200 reactor; Бутаковские чтения
  द्वारा: Odii C. J.
  प्रकाशित: (2023)
• Validation of safety parameters of VVER-1200 using PCTran simulator; Бутаковские чтения
  द्वारा: Odii C. J.
  प्रकाशित: (2024)
• The effect of subcooled water parameters on thermal-hydraulic characteristics for VVER reactor; Thermal Science; Vol. 29, iss.1
  द्वारा: Korotkikh A. G. Aleksandr Gennadievich
  प्रकाशित: (2025)
• Prediction of minimum departure from nucleate boiling ratio in VVER-1200 reactor core using heat balance and direct substitution methods; Перспективы развития фундаментальных наук; Т. 1 : Физика
  द्वारा: Odii C. J.
  प्रकाशित: (2024)