|Code for neutronic simulations (name+short description)||MCNP –Probabilistic code||DYN3D-MSR (3D neutron kinetics with precursor transport)||Monte Carlo MCNP-4B code coupled by a special developed interface with the ORIGEN2.1 code||SERPENT2 (Monte Carlo) ERANOS/EQL-3D (deterministic)||DYNAMOSS deterministic code||DALTON (3-D time dependent diffusion with precursor transport)|
|Neutronic simulations: include reactor evolution?||Yes – Neutronic code coupled to the REM in-house code for materials evolution||materials evolution HELIOS cell code with scriptbased execution for reactor evolution calc.||Yes–depletion equations solved by ORIGEN2.1 using the one-group cross section obtained from MCNP-4B||(S) Yes: purpose made extension of b- up routines (E) Yes: extension of EQL-3D procedure||No ? only short term dynamics included (no burnup)||Yes ? own made ORIGEN-like program LOWFAT|
|Code availability (date)/validation (yes/no + on which system)||Used since 15 yr/tested on MSRE and MSBR||Code available; validated within MOST project||Used notably for the studies and definition of the MOSART concept||(S) The extension is available since now upon request, will be implemented in the official version of SERPENT-2 Code-to-code assessment between the two codes||Developed during MOST and ALISIA project, benchmarked during MOST project||MSRE (Neutronic)+ code-to-code (Burnup)|
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