2001•Annals of Nuclear EnergyRequires access

Validation of coupled neutron kinetic/thermal–hydraulic codes. Part 1: Analysis of a VVER-1000 transient (Balakovo-4)

S. Mittag, S. Kliem, F.‐P. Weiß, Riitta Kyrki-Rajamäki, Helmi Hämäläinen, Siegfried Langenbuch, Sergey Danilin, J. Hádek, Gy. Hegyi, A.V. Kuchin, D. Panayotov

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Key concepts: VVER, Thermal hydraulics, Nuclear engineering, Transient (computer programming), Coolant, Pressurized water reactor, Environmental science, Neutron transport

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Validation of coupled neutron kinetic/thermal–hydraulic codes. Part 1: Analysis of a VVER-1000 transient (Balakovo-4) — Research Paper | ScholarLens