This work has been carried out within the framework of the STREP ELSY (European Lead cooled System, inserted in the 6th EU FP) that aims at investigating the technical and economical feasibility of a 600 MWe power reactor by adopting new and simplified engineered technical features. The LFR (one of the six promising advanced reactors being considered by the GIF, Generation-IV International Forum) features a fast-neutron spectrum and a closed fuel cycle by means o! a suitable conversion of fertile Uranium. Meantime it can also burn its own MAs (at least). This report (Deliverable D6, Task 2.2, WP 2) deals with the preliminary neutronic analysis of a 1500 MWth, core made by open square FAs (the backup wrapped hexagonal option is investigated in parallel). The main part of this work is devoted to several scoping calculations that have permitted to reach the core design solution sketched at chapter 8 and the detailed drawings of each part of the reactor inside the barrel (chapter 14, Appendix F).

ELSY Open Square Fuel Assembly Design and Drawings

Grasso, G.;Sarotto, M.
2008-11-04

Abstract

This work has been carried out within the framework of the STREP ELSY (European Lead cooled System, inserted in the 6th EU FP) that aims at investigating the technical and economical feasibility of a 600 MWe power reactor by adopting new and simplified engineered technical features. The LFR (one of the six promising advanced reactors being considered by the GIF, Generation-IV International Forum) features a fast-neutron spectrum and a closed fuel cycle by means o! a suitable conversion of fertile Uranium. Meantime it can also burn its own MAs (at least). This report (Deliverable D6, Task 2.2, WP 2) deals with the preliminary neutronic analysis of a 1500 MWth, core made by open square FAs (the backup wrapped hexagonal option is investigated in parallel). The main part of this work is devoted to several scoping calculations that have permitted to reach the core design solution sketched at chapter 8 and the detailed drawings of each part of the reactor inside the barrel (chapter 14, Appendix F).
Rapporto tecnico;Neutronica
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Utilizza questo identificativo per citare o creare un link a questo documento: http://hdl.handle.net/20.500.12079/5304
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