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The ELSY Project
This paper presents the current status of the development of ELSY (the acronym for the European Lead-cooled System). The ELSY reference design is a 600 MWe pool-type reactor cooled by pure lead. This concept is under development since September 2006, and is sponsored by the Sixth Framework Programme of EURATOM. The ELSY project, coordinated by Ansaldo Nucleare, is being performed by a consortium consisting of twenty organizations including seventeen from Europe, two from Korea and one from the USA. The partners are from industry, research organisations and universities. ELSY aims to demonstrate the possibility of designing a fast critical reactor using simple engineered technical features, whilst fully complying with the Generation IV goals of sustainability, economics, safety, proliferation resistant and physical protection. Compactness of the reactor building is possible due to the elimination of the Intermediate Cooling System, and the adoption of innovative DHR systems. Among the critical issues, the effect of the large mass of lead has been considered; this assessment allows being very confident in the feasibility of the reactor vessel and its support. ; JRC.F.4-Nuclear design safety
The ELSY Project
This paper presents the current status of the development of ELSY (the acronym for the European Lead-cooled System). The ELSY reference design is a 600 MWe pool-type reactor cooled by pure lead. This concept is under development since September 2006, and is sponsored by the Sixth Framework Programme of EURATOM. The ELSY project, coordinated by Ansaldo Nucleare, is being performed by a consortium consisting of twenty organizations including seventeen from Europe, two from Korea and one from the USA. The partners are from industry, research organisations and universities. ELSY aims to demonstrate the possibility of designing a fast critical reactor using simple engineered technical features, whilst fully complying with the Generation IV goals of sustainability, economics, safety, proliferation resistant and physical protection. Compactness of the reactor building is possible due to the elimination of the Intermediate Cooling System, and the adoption of innovative DHR systems. Among the critical issues, the effect of the large mass of lead has been considered; this assessment allows being very confident in the feasibility of the reactor vessel and its support. ; JRC.F.4-Nuclear design safety
The ELSY Project
CINOTTI Luciano (Autor:in) / LOCATELLI Giuliano (Autor:in) / AIT ABDERRAHIM Hamid (Autor:in) / MONTI Stefano (Autor:in) / BENAMATI Gianluca (Autor:in) / WIDER HARTMUT (Autor:in) / STRUWE Dankward (Autor:in) / ORDEN Alfredo (Autor:in)
14.02.2008
Sonstige
Elektronische Ressource
Englisch
DDC:
690
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