This work was carried out in the CDT/FASTEF EU FP7 project: it deals with the preliminary core design of MYRRHA-FASTEF, a 100 MW LBE cooled reactor (working in both criticai and sub-critical modes) that should be able to demonstrate transmutation and associated technology. Besides the analyses dealing with the 100 MW-69 FA FASTEF criticai core (~35 wt.% Pu mass content in the MOX pellet), some additional investigations were performed in order to supply an extended data set for the CDT in Mol (SCK-CEN research centre, Belgium). By adopting the ERANOS deterministic code, the neutronic study here summarised reports the results of a Pu vector sensitivity analysis (par. 2) and gives some indications concerning the possibility: - to reduce the core barrel diameter, by adopting 121 SA in the layout (instead of 151 SA, par. 3); - to adopt a 30 wt.% Pu mass content, investigated for both criticai (par. 4) and sub-critical (par. 5) modes; - to adopt MOX pellets with enriched U (instead of natural U, par. 8). Furthermore, some safety issues related to possible FA loading errors during refuelling were investigated (par. 6).

Scoping neutronic investigations for MYRRHA critical (and sub-critical) core

Sarotto, M.
2011

Abstract

This work was carried out in the CDT/FASTEF EU FP7 project: it deals with the preliminary core design of MYRRHA-FASTEF, a 100 MW LBE cooled reactor (working in both criticai and sub-critical modes) that should be able to demonstrate transmutation and associated technology. Besides the analyses dealing with the 100 MW-69 FA FASTEF criticai core (~35 wt.% Pu mass content in the MOX pellet), some additional investigations were performed in order to supply an extended data set for the CDT in Mol (SCK-CEN research centre, Belgium). By adopting the ERANOS deterministic code, the neutronic study here summarised reports the results of a Pu vector sensitivity analysis (par. 2) and gives some indications concerning the possibility: - to reduce the core barrel diameter, by adopting 121 SA in the layout (instead of 151 SA, par. 3); - to adopt a 30 wt.% Pu mass content, investigated for both criticai (par. 4) and sub-critical (par. 5) modes; - to adopt MOX pellets with enriched U (instead of natural U, par. 8). Furthermore, some safety issues related to possible FA loading errors during refuelling were investigated (par. 6).
Rapporto tecnico;Fisica dei reattori nucleari;Neutronica
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Utilizza questo identificativo per citare o creare un link a questo documento: https://hdl.handle.net/20.500.12079/5356
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