Open Access
Table 6
Numerical tools dedicated to neutronic and evolution calculations of the MSFR [17, 21, 26, 29–44].
| Contribution\Partner | CNRS | FZD–HZDR | KI | POLIMI | POLITO | TUD |
|---|---|---|---|---|---|---|
| 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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