| 4 | | || 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 \\ |
| 5 | | 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, 400px, title=Neutron density distribution in the BME Training reactor calculated by GUARDYAN)]] ''Neutron density distribution in the BME Training reactor calculated by GUARDYAN'' || |
| 6 | | |
| 7 | | [wiki:GuarDyan_features = Keep reading ] |
| 8 | | = Features |
| 9 | | |
| 10 | | 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. |
| 11 | | |
| 12 | | [wiki:GuarDyan_features Keep reading ] on Guardyan. |
| 13 | | |
| 14 | | || [[Image(VVER440_v1.png, 100%)]] ||[[Image(woodcock_elastic-scatter.3.png, 100%)]] || [[Image(hexagon_lattice_v3.jpg, 100%)]] || |
| 15 | | || [[Image(hexy-hexyk.jpg, 80%)]] || |
