Title of article
ASTEC V2.0 reactor applications on French PWR 900 MWe accident sequences and comparison with MAAP4
Author/Authors
Lombard، نويسنده , , Virginie and Azarian، نويسنده , , Garo and Ducousso، نويسنده , , Erik and Gandrille، نويسنده , , Pascal، نويسنده ,
Issue Information
روزنامه با شماره پیاپی سال 2014
Pages
5
From page
219
To page
223
Abstract
In the frame of the SARNET Severe Accident Network of Excellence an important task of partners is the assessment of the ASTEC integral code, considered today as the European reference code for evaluation of the source term. A code-to-code comparison between ASTEC V2.0 rev1 and MAAP 4.0.7 code versions has been performed by AREVA NP SAS on a French PWR 900 MWe. Two transients have been analyzed, focussing on in-vessel phenomena: total loss of feedwater (H2 sequence in the French nomenclature) and total loss of onsite and offsite power (H3 sequence). The detailed analysis shows an overall good agreement between both code results on thermal-hydraulics, hydrogen production and core degradation phenomena.
Journal title
Nuclear Engineering and Design Eslah
Serial Year
2014
Journal title
Nuclear Engineering and Design Eslah
Record number
1594603
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