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.2013.10.010Additional 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
INIS
- Country of Publication
- Netherlands
- Country of Input or Organization
- International Atomic Energy Agency (IAEA)
- INIS RN
- 46023324
- Subject category
- S42: ENGINEERING;
- Descriptors DEI
- FEEDWATER; HYDROGEN PRODUCTION; LOSS OF COOLANT; PWR TYPE REACTORS; REACTOR ACCIDENT SIMULATION; REACTOR ACCIDENTS; REACTOR VESSELS; THERMAL HYDRAULICS
- Descriptors DEC
- ACCIDENTS; CONTAINERS; ENRICHED URANIUM REACTORS; FLUID MECHANICS; HYDRAULICS; HYDROGEN COMPOUNDS; MECHANICS; OXYGEN COMPOUNDS; POWER REACTORS; REACTOR ACCIDENTS; REACTORS; SIMULATION; THERMAL REACTORS; WATER; WATER COOLED REACTORS; WATER MODERATED REACTORS
Optional Information
- Copyright
- Copyright (c) 2013 Elsevier Science B.V., Amsterdam, The Netherlands, All rights reserved.