Title of article :
ASTEC V2 severe accident integral code main features, current V2.0 modelling status, perspectives
Author/Authors :
Chatelard، نويسنده , , P. and Reinke، نويسنده , , N. T. Arndt، نويسنده , , S. and Belon، نويسنده , , S. and Cantrel، نويسنده , , L. and Carenini، نويسنده , , L. and Chevalier-Jabet، نويسنده , , K. and Cousin، نويسنده , , F. and Eckel، نويسنده , , J. and Jacq، نويسنده , , F. and Marchetto، نويسنده , , C. and Mun، نويسنده , , C. and Piar، نويسنده , , L.، نويسنده ,
Issue Information :
روزنامه با شماره پیاپی سال 2014
Pages :
17
From page :
119
To page :
135
Abstract :
The severe accident integral code ASTEC, jointly developed since almost 20 years by IRSN and GRS, simulates the behaviour of a whole nuclear power plant under severe accident conditions, including severe accident management by engineering systems and procedures. Since 2004, the ASTEC code is progressively becoming the reference European severe accident integral code through in particular the intensification of research activities carried out in the frame of the SARNET European network of excellence. rst version of the new series ASTEC V2 was released in 2009 to about 30 organizations worldwide and in particular to SARNET partners. With respect to the previous V1 series, this new V2 series includes advanced core degradation models (issued from the ICARE2 IRSN mechanistic code) and necessary extensions to be applicable to Gen. III reactor designs, notably a description of the core catcher component to simulate severe accidents transients applied to the EPR reactor. Besides these two key-evolutions, most of the other physical modules have also been improved and ASTEC V2 is now coupled to the SUNSET statistical tool to make easier the uncertainty and sensitivity analyses. The ASTEC models are today at the state of the art (in particular fission product models with respect to source term evaluation), except for quenching of a severely damage core. the need to develop an adequate model for the reflooding of a degraded core, the main other mean-term objectives are to further progress on the on-going extension of the scope of application to BWR and CANDU reactors, to spent fuel pool accidents as well as to accidents in both the ITER Fusion facility and Gen. IV reactors (in priority on sodium-cooled fast reactors) while making ASTEC evolving towards a severe accident simulator constitutes the main long-term objective. aper presents the status of the ASTEC V2 versions, focussing on the description of V2.0 models for water-cooled nuclear plants.
Journal title :
Nuclear Engineering and Design Eslah
Serial Year :
2014
Journal title :
Nuclear Engineering and Design Eslah
Record number :
1594583
Link To Document :
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