GUARDYAN

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

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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GUARDYAN (GPU Assisted Reactor Dynamic Analysis) fejlesztői segédlete itt található.