ASTEC V2.0 reactor applications on French PWR 900 MWe accident sequences and comparison with MAAP4

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• 作者：Virginie Lombard ; Garo Azarian ; Erik Ducousso ; Pascal Gandrille ; ^{pascal.gandrille@areva.com" class="auth_mail}
• 刊名：Nuclear Engineering and Design
• 出版年：June 2014
• 年：2014
• 卷：272
• 期：Complete
• 页码：219-223
• 全文大小：1846 K

文摘

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.