Coarse-Mesh Flux-Expansion Method for the Analysis of Space-Time Effects in Large Light Water Reactor Cores

The Parareal in Time Algorithm Applied to the Kinetic Neutron Diffusion Equation

“…At each time step, a Gauss-Seidel iteration is used on the energy groups and the spatial discretization is done with RT-1 finite elements (see [4]). The geometry and history that have been chosen for the simulation is the so called TWIGL benchmark that represents a rod withdrawal (see [8]). The geometry of the core is three-dimensional.…”

Analysis of the SPERT-III E-Core Using ANCK Code with the Chord Weighting Method

“…In order to investigate this behavior under transient, ANCK and ANCK/ MIDAC have been used to calculate the OECD/NEA RIA benchmark, 7,8) the LMW benchmark, 9) and the uncontrolled withdrawal of control rods from the zero power benchmark. 10,11) In addition, the capabilities of the coupled code ANCK/MIDAC using the MSLB benchmark problem 12,13) have also been confirmed.…”

Analysis of the Main Steam Line Break Benchmark (Phase II) Using ANCK/MIDAC Code

“…6) ANCK calculates the enthalpies of each fuel rod in the core using the pin power reconstruction method under transient conditions. The verification of the ANCK code has been performed using the following well-known benchmark problems: the 3D LMW LWR benchmark, 7) the NEACRP PWR rod ejection benchmarks, 8,9) and the PWR uncontrolled withdrawal of the CR benchmark. 10,11) From these verifications, it has been confirmed that ANCK has a good reliability for the kinetics engine of ANCK/MIDAC.…”