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 critical and sub-critical modes) that should be able to demonstrate transmutation and associated technology. The report summarizes the presentation done by the author at the International Workshop on “Innovative Nuclear Reactors cooled by Heavy Liquid Metals: Status and Perspectives”, organised by ENEA-MSE and EU FP7 EC SEARCH on April 17-20th 2012, in Pisa (Italy). He showed briefly the main outcome of the WP2 Task 2.2 in the FP7 EU project CDT, represented by the MYRRHA-FASTEF FA / core design. The neutronic and TH analyses presented refer to both critical (34.5 wt.% Pu mass content) and sub-critical (30 wt.% Pu mass content) operational modes.
An outcome of the EU FP7 CP CDT: the MYRRHA-FASTEF FA/core design
Sarotto, Massimo
2012-07-17
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 critical and sub-critical modes) that should be able to demonstrate transmutation and associated technology. The report summarizes the presentation done by the author at the International Workshop on “Innovative Nuclear Reactors cooled by Heavy Liquid Metals: Status and Perspectives”, organised by ENEA-MSE and EU FP7 EC SEARCH on April 17-20th 2012, in Pisa (Italy). He showed briefly the main outcome of the WP2 Task 2.2 in the FP7 EU project CDT, represented by the MYRRHA-FASTEF FA / core design. The neutronic and TH analyses presented refer to both critical (34.5 wt.% Pu mass content) and sub-critical (30 wt.% Pu mass content) operational modes.I documenti in IRIS sono protetti da copyright e tutti i diritti sono riservati, salvo diversa indicazione.
