Validation of coupled neutron kinetic/thermal-hydraulic codes. Part 2: Analysis of a VVER-440 transient (Loviisa-1)

Annals of Nuclear Energy

Volumn 29, Issue 3, 2002, Pages 255-269

  Hamalainen A ^a   Kyrki Rajamaki R ^a   Mittag, S ^a   Kliem, S ^b   Weiss, F P ^b   Langenbuch, S ^c   Danilin, S ^d   Hadek, J ^e   Hegyi, G ^f  

^a VTT TECHNICAL RESEARCH CENTRE OF FINLAND   (Finland)

^b INSTITUTE OF ION BEAM PHYSICS AND MATERIALS RESEARCH   (Germany)

^c GESELLSCHAFT FÜR ANLAGEN UND REAKTORSICHERHEIT GRS MBH   (Germany)

^d KURCHATOV INSTITUTE   (Russian Federation)

^e NUCLEAR RESEARCH INSTITUTE   (Czech Republic)

^f KFKI ATOMIC ENERGY RESEARCH INSTITUTE   (Hungary)

Author keywords

[No Author keywords available]

Indexed keywords

COMPUTER PROGRAM LISTINGS; NEUTRONS; REACTOR CORES; TURBOGENERATORS;

NEUTRON KINETIC THERMAL-HYDRAULIC CODES;

NUCLEAR FUELS;

EID: 0036462743     PISSN: 03064549     EISSN: None     Source Type: Journal    
DOI: 10.1016/S0306-4549(01)00039-1     Document Type: Article

References (7)

1. Coupling of the thermohydraulic code ATHLET with the neutron kinetic core model DYN3D
2. Improvement of plant transient analysis for VVER by coupling KIKO3D with ATHLET
3. Time dependent spatial neutron kinetic algorithm for BIPR8 and its verification
4. Development and validation of the fast running thermohydraulic model SMABRE for simulator purposes
5. Validation of coupled neutron kinetic/thermal-hydraulic codes. Part 1: Analysis of a VVER-1000 transient (Balakovo-4)
6. Methodology, status and plans for development and assessment of the code ATHLET