Utvärdering av beräkningskoden APROS för användning i inneslutningsanalyser

• Main Author: Höök, Peter
• Format: Others
• Language: Swedish
• Published: Uppsala universitet, Tillämpad kärnfysik 2014
• Subjects: kärnkraft; säkerhetsanalys; APROS; reaktorinneslutning; inneslutningsanalys
• Online Access: http://urn.kb.se/resolve?urn=urn:nbn:se:uu:diva-230357

At Forsmark nuclear power plant the rather old-fashioned software COPTA is used in containment safety analysis. There exists a desire within the organisation to introduce a more modern software with ability to more detailed modeling and increased usability. The goal of this thesis was to evaluate the software APROS in containment safety analysis. APROS models describing one of the containments at Forsmark NPP have been developed. Two simulations of typical containment incidents, one of them a large pipe break, have been made where containment safety parameters such as pressure and temperature are studied. Results are analyzed and verified against results from corresponding COPTA models. The other part of the evaluation includes a listing of detected possibilities and limitations with APROS regarding containment modeling in general. Overall the developed APROS models show a good agreement with results from corresponding COPTA models. Observed differences can in most cases be explained by minor differences in model choices, mostly concerning flow patterns and heat transfer. APROS has many similarities with COPTA regarding the main calculation and modeling methods but APROS can in most cases be seen as the more sophisticated software with more possibilities regarding modeling complexity. The general conclusion is that APROS shows good potential to be used in containment safety analysis.