Kerntechnik

Simulation of standard temperature control indications at the outlet of a fuel assembly of VVER1000 reactor of Rostov NPP unit No. 2

Extension of nodal diffusion solver of Ants to hexagonal geometry

C-PORCA 7: a nodal diffusion reactor calculation code to support off-line and on-line core analysis at Paks nuclear power plant

Adaptation of the gas gap simplified model in DYN3D code to new types of fuel

A procedure for verification of Studsvik's spent nuclear fuel code SNF

Thermal hydraulic characteristics of two-phase natural circulation for secondary side passive residual heat removal system

TRACE simulations of IIST cooldown experiments

Flow and heat transfer characteristics in rough micro-channels

Benchmark study of OPAL research reactor using MCNP codes

CFD code-to-code benchmarking on simulation of fire and smoke propagation for nuclear applications