This paper takes the move from a previous work in which an erbia fully poisoned PWR fuel assembly was characterized from a neutronic point of view by means of the deterministic transport code APOLLO2. The neutronic performance of that assembly, developed according to the Erbia-credit Super High Burnup fuel concept, was found to be, up to 120 GWd/MTU, at least as good as that of a conventional FA enriched to 5 wt% in 235U in terms of some fundamental properties. Since APOLLO2 is not qualified at those burnup and enrichment values, the results obtained with APOLLO2 deserved to be investigated. In this context, the values of criticality and isotope concentrations as a function of burnup obtained with APOLLO2 have been compared with those obtained with the Monte Carlo transport code MCNP6.1. This comparison has been carried out using in MCNP6.1 two neutron cross section libraries, namely JEFF-3.1.2 and JEFF-3.2, since no library consistent with the CEA2005v4.1.2 used in APOLLO2 is available. The degree of discrepancy between the results obtained with the two codes is of the same order of magnitude of that related to a conventional FA enriched to 5 wt% in 235U.
Comparison between APOLLO2 and MCNP6 on depletion calculations for an Er-SHB PWR fuel assembly
Pergreffi R.;Rocchi F.;Guglielmelli A.;Console Camprini P.
2022-01-01
Abstract
This paper takes the move from a previous work in which an erbia fully poisoned PWR fuel assembly was characterized from a neutronic point of view by means of the deterministic transport code APOLLO2. The neutronic performance of that assembly, developed according to the Erbia-credit Super High Burnup fuel concept, was found to be, up to 120 GWd/MTU, at least as good as that of a conventional FA enriched to 5 wt% in 235U in terms of some fundamental properties. Since APOLLO2 is not qualified at those burnup and enrichment values, the results obtained with APOLLO2 deserved to be investigated. In this context, the values of criticality and isotope concentrations as a function of burnup obtained with APOLLO2 have been compared with those obtained with the Monte Carlo transport code MCNP6.1. This comparison has been carried out using in MCNP6.1 two neutron cross section libraries, namely JEFF-3.1.2 and JEFF-3.2, since no library consistent with the CEA2005v4.1.2 used in APOLLO2 is available. The degree of discrepancy between the results obtained with the two codes is of the same order of magnitude of that related to a conventional FA enriched to 5 wt% in 235U.I documenti in IRIS sono protetti da copyright e tutti i diritti sono riservati, salvo diversa indicazione.
