This work was carried out in the framework of the CDT/FASTEF EU FF7 project: it deals with the preliminary FA/core design far MYRRHA-FASTEF, a 100 MW LBE cooled reactor (working in both critical and sub-critical modes) that should be able la demonstrate transmutation and associated technology. The analysis concerns the neutronic characterisation at BoL of the 'reference' critical core (33 wt. % Pu mass content, 68 FA, 7 central IPS), together with the individuation of the possible boundary working conditions for the (critical) irradiation facility: a minimum core (42 FA without IPS) almost critical at BoL and a maximum core (70 FA with 11 IPS) critical at the EaC of the equilibrium sub-cycle. Based on these (and other) evaluations, done with the ERANOS ver. 2.1 deterministic code, some important remarks about the (total and fast) flux Ievels obtained, the care pressure drop, the dpa level on barrel, the Fu mass content and the dummy structure are reported. The second part of the presentation (done at the WP2 meeting, on 14-15 October 2010 at the SCK-CEN Headquarters in Brussels) defines some details of the work plan for the WP2 - Task 2.2 (in which ENEA is responsible).

The MYRRHA-FASTEF critical core: neutronic estimations at BoL with the ERANOS deterministic code

Sarotto, M.
2010-11-29

Abstract

This work was carried out in the framework of the CDT/FASTEF EU FF7 project: it deals with the preliminary FA/core design far MYRRHA-FASTEF, a 100 MW LBE cooled reactor (working in both critical and sub-critical modes) that should be able la demonstrate transmutation and associated technology. The analysis concerns the neutronic characterisation at BoL of the 'reference' critical core (33 wt. % Pu mass content, 68 FA, 7 central IPS), together with the individuation of the possible boundary working conditions for the (critical) irradiation facility: a minimum core (42 FA without IPS) almost critical at BoL and a maximum core (70 FA with 11 IPS) critical at the EaC of the equilibrium sub-cycle. Based on these (and other) evaluations, done with the ERANOS ver. 2.1 deterministic code, some important remarks about the (total and fast) flux Ievels obtained, the care pressure drop, the dpa level on barrel, the Fu mass content and the dummy structure are reported. The second part of the presentation (done at the WP2 meeting, on 14-15 October 2010 at the SCK-CEN Headquarters in Brussels) defines some details of the work plan for the WP2 - Task 2.2 (in which ENEA is responsible).
Rapporto tecnico;Fisica dei reattori nucleari;Neutronica
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Utilizza questo identificativo per citare o creare un link a questo documento: http://hdl.handle.net/20.500.12079/6884
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