Comparison of two modern approaches for MBDA calculations of RBMK-type reactors

Kerntechnik

Volumn 69, Issue 3, 2004, Pages 92-98

  Urbonas, Rolandas ^a   Kaliatka, Algirdas ^a   Ušpuras, Eugenijus ^a  

^a LITHUANIAN ENERGY INSTITUTE   (Lithuania)

Author keywords

[No Author keywords available]

Indexed keywords

BOUNDARY CONDITIONS; COMPUTATIONAL METHODS; ENERGY EFFICIENCY; ESTIMATION; FLOW OF FLUIDS; NUCLEAR FUELS; NUCLEAR REACTOR ACCIDENTS;

BEST-ESTIMATES CODES; ENERGY EMISSION; FUEL CHANNELS; SAFETY MARGINS;

NUCLEAR POWER PLANTS;

EID: 2942513043     PISSN: 09323902     EISSN: None     Source Type: Journal    
DOI: 10.3139/124.100195     Document Type: Review

References (7)

1. Almenas, K.; Kaliatka, A.; Uspuras E.: Ignalina RBMK-1500. A Source Book. Extended and updated version., Lithuanian Energy Institute, Kaunas, 1998
2. Kaliatka, A.; Uspuras E.: Benchmark analysis of main circulation pump trip events at the Ignalina NPP using RELAPS code: Nuclear Engineering and Design 202 (2000) 109
3. The RELAPS Code Development Team: RELAP5/MOD3 Code Manual. Code Structure, System Models, and Solution Methods, Volume 1, NUREG/CR-5535, INEL-95/0174, 1995
4. International Atomic Energy Agency: Accident and transient analysis of RBMK nuclear power plants, Appendix C, Vienna, 2000
5. Kaliatka, A.; Uspuras, E.: Thermal-hydraulic analysis of accidents leading to local coolant flow rate decrease in the main circulation circuit of RBMK-1500. Nuclear Engineering and Design 217 (2002) 91
6. Kloos, M.; Hofer, E.: SUSA Version 3.2. User's Guide and Tutorial, 1999
7. Glaeser, H. G.: Uncertainty Evaluation of Thermal-Hydraulic Code Results. Int. Meeting on "Best-Estimate" Methods in Nuclear Installation Safety Analysis (BE-2000), Washington DC, USA, 2000