A simulation of a steam generator tube rupture in a VVER-1000 plant

Energy Conversion and Management

Volumn 49, Issue 7, 2008, Pages 1972-1980

  Nematollahi, M R ^a   Zare, A ^a  

^a SHIRAZ UNIVERSITY   (Iran)

Author keywords

Steam generator; Tube rupture and thermo hydraulics; VVER 1000

Indexed keywords

COMPUTER SIMULATION; COOLANTS; HYDRAULIC MODELS; NUCLEAR ENERGY; NUCLEAR REACTOR ACCIDENTS; STEAM GENERATORS;

HYDRAULICS PARAMETERS; NUCLEAR SAFETY; PLANT PARAMETERS; TRANSIENT TIME; TUBE RUPTURE;

NUCLEAR POWER PLANTS;

EID: 43849087380     PISSN: 01968904     EISSN: None     Source Type: Journal    
DOI: 10.1016/j.enconman.2007.12.018     Document Type: Article

References (4)

1. Federal Agency on Nuclear Energy of Russia. Final safety analysis report for BNPP, chapter 15, accident analysis, book 4, Revision 0, Moscow; 2005.
2. Auvinen A., Jokiniemi J.K., and Routarno T. Steam generator tube rupture (SGTR) scenarios. J Nucl Eng Des 235 (2004) 457-472
3. Kuroda T, Watanabe T. Break flow modeling for a steam generator tube rupture (SGTR) incident in a pressurized water reactor (PWR), Japan Atomic Energy Research Institute; 1993.
4. Groudev P.P., Gencheva R.V., Stefanova A.E., and Pavlova M.P. RELAP5/MOD3.2 investigation of primary-to-secondary reactor coolant leakage in VVER-440. J Nucl Eng Des 31 (2004) 961-974