GUARDYAN

GUARDYAN (GPU Assisted Reactor Dynamic Analysis) is a continuous energy Monte Carlo (MC) neutron transport code developed at Budapest University of Technology and Economics (​BME). It targets to solve time-dependent problems related to fission reactors with the main focus on simulating and analyzing short transients. The key idea of GUARDYAN is a massively parallel execution structure making use of advanced programming possibilities available on CUDA (Compute Unified Device Architecture) enabled GPUs (Graphics Processing Units).

GUARDYAN (GPU Assisted Reactor Dynamic Analysis) is a continuous energy Monte Carlo (MC) neutron transport code developed at Budapest University of Technology and Economics (​BME). It targets to solve time-dependent problems related to fission reactors with the main focus on simulating and analyzing short transients. The key idea of GUARDYAN is a massively parallel execution structure making use of advanced programming possibilities available on CUDA (Compute Unified Device Architecture) enabled GPUs (Graphics Processing Units).

Neutron density distribution in the BME Training reactor calculated by GUARDYAN

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Features

GUARDYAN (GpU Assisted Reactor DYnamic ANalysis) is a Monte Carlo based neutrontransport program running on GPU (Graphics Processing Unit) for simulating reactor transients. The simulation tracks neutrons in a three dimensional space bounded by second degree surfaces while they interact with the isotopes present in the region. Cross Section Data may be given in ACE (A Compact ENDF ) format coming from ENDF (Evaluated Nuclear Data File) cross section table. The current version of the code supports time- and temperature dependent cross sections, thermal feedback is included in future releases.

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