Published June 2014 | Version v1
Journal article

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

Description

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

Availability note (English)

Available from http://dx.doi.org/10.1016/j.nucengdes.2013.10.010

Additional details

Identifiers

DOI
10.1016/j.nucengdes.2013.10.010;
PII
S0029-5493(13)00557-8;

Publishing Information

Journal Title
Nuclear Engineering and Design
Journal Volume
272
Journal Page Range
p. 219-223
ISSN
0029-5493
CODEN
NEDEAU

Optional Information

Copyright
Copyright (c) 2013 Elsevier Science B.V., Amsterdam, The Netherlands, All rights reserved.