RELAP5/MOD3.2 investigation of primary-to-secondary reactor coolant leakage in VVER440

Annals of Nuclear Energy

Volumn 31, Issue 9, 2004, Pages 961-974

  Groudev, Pavlin P ^a   Gencheva, Rositsa V ^a   Stefanova, Antoaneta E ^a   Pavlova, Malinka P ^a  

^a INSTITUTE FOR NUCLEAR RESEARCH AND NUCLEAR ENERGY   (Bulgaria)

Author keywords

[No Author keywords available]

Indexed keywords

COOLANTS; COOLING SYSTEMS; DATA REDUCTION; HYDRAULICS; MATHEMATICAL MODELS; PRESSURIZED WATER REACTORS; PUMPS; STEAM GENERATORS; THERMOANALYSIS;

REACTOR COOLANT SYSTEMS (RCS); THERMAL-HYDRAULIC ANALYSIS;

NUCLEAR POWER PLANTS;

EID: 1542790439     PISSN: 03064549     EISSN: None     Source Type: Journal    
DOI: 10.1016/j.anucene.2004.01.001     Document Type: Article

References (5)

1. Borissenko, V., Fedorchenko, S., Krushynsky, A., 2000. Rivne NPP Standard Problem Definition Report - Rivne NPP Unit 1 Short Description and Transient Data Base. National Taras Shevchenko University of Kyiv, pp. 2-55.
2. Borissenko, V., Fedorchenko, S., Krushynsky, A. 2002. Rivne NPP Standard Problem Analysis Report - Description of Rivne NPP Unit 1 RELAP Model. National Taras Shevchenko University of Kyiv, pp. 2-118.
3. Borissenko, V., Krushynsky, A. 2003. Rivne NPP VVER-440 Thermal-Hydraulic Standard Problem Analysis Final Report - Steam Collector Rupture Transient. National Taras Shevchenko University of Kyiv, pp. 15-44.
4. Elkin, I.D., et al. 1997. Guideline For Performing Code Validation Within The DOE International Nuclear Safety Center (INSC). US/Russian International Nuclear Safety Center, Argonne-Chicago and Moscow, pp. 1-6.
5. Fletcher, C.D., Schultz, R.R., 1995. RELAP5/MOD3 Code Manual. User's Guidelines. NUREG/CR-5535, INEL-95/0174, Vol.5, Rev. 1.