Open Access

Table 6

Numerical tools dedicated to neutronic and evolution calculations of the MSFR [17, 21, 26, 2944].

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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