The conceptual design of the Advanced Lead Fast Reactor European Demonstrator (ALFRED) is under development within the LEADER project to meet the safety objectives of Gen-IV nuclear energy systems. This paper presents the main results of the safety analysis for beyond design basis conditions, namely design extension conditions (DEC), which include the failure of prevention and mitigation systems, like the reactor scram in the so-called unprotected transients. The main objective of this analysis is to evaluate the impact of the core and plant design features on the intrinsic safety behaviour of the ALFRED reactor. Several computer codes: SIM-LFR, RELAP5, CATHARE, SPECTRA and TRACE are applied to evaluate the consequences of representative unprotected accident scenarios such as Loss-of-Flow, Loss-of-Heat-Sink and Reactivity initiated accidents. Additionally, the consequences of steam generator tube rupture and partial sub-assembly flow blockage events are assessed by means of appropriate fluid-dynamic codes.
BANDINI G.;
BUBELIS E.;
SCHIKORR M;
STEMPNIEVICZ M.H.;
LAZARO CHUECA Aurelio;
TUCEK Kamil;
KUDINOV P.;
KÖÖP K.;
JELTSOV M.;
MANSANI L.;
2015-09-03
IAEA
JRC80222
978-92-0-104114-2,
0074-1884,
http://www-pub.iaea.org/books/IAEABooks/10682/Fast-Reactors-and-Related-Fuel-Cycles-Safe-Technologies-and-Sustainable-Scenarios-FR13-Proceedings-of-an-International-Conference-on-Fast-Reactors-and-Related-Fuel-Cycles-Paris-France-4-7-March-2013,
https://publications.jrc.ec.europa.eu/repository/handle/JRC80222,
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