= 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 ([http://www.reak.bme.hu 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). ||[[Image(BME_OR_1e-6s_n2e24_neutrondensity_Guardyan_v3r.jpg, 100%)]] ''Neutron density distribution in the BME Training reactor calculated by GUARDYAN'' ||

The use of GPU architectures reaquire 

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. 

[wiki:GuarDyan_features Keep reading ] on Guardyan.

 || [[Image(VVER440_v1.png, 100%)]] ||[[Image(woodcock_elastic-scatter.3.png, 100%)]] ||  [[Image(hexagon_lattice_v3.jpg, 100%)]] ||
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GUARDYAN (GPU Assisted Reactor Dynamic
Analysis) fejlesztői segédlete [wiki:GuarDyan_fejlesztoi itt található].


[[Image(NRDI.jpg, 80%)]]