Review of simulation codes and methodologies for LOCA and SGTR
Authors/Creators
- ARKOMA Asko1
- SZOGRADI Marton1
- LESKINEN Joona1
- BUSSER Vincent2
- JACQ François2
- BELON Sébastien2
- ADORNI Martina3
- MASCARI Fulvio4
- EDERLI Stephano4
- GUMENYUK Dmytro5
- ZHABIN Oleg5
- OVDIIENKO Iurii5
- LISHCHUK Ruslan6
- SHOLOMITSKY Stanislav6
- Müllner Nikolaus7
- KULACSY Katalin8
- Hozer Zoltan8
- Kecek Adam9
- JOBST Matthias10
- HERRANZ Luis11
- FERIA Francisco11
- IGLESIAS Rafael11
- KALIATKA Tadas12
- VAN-UFFELEN Paul13
- BRADT Paul14
- 1. VTT
- 2. IRSN
- 3. BEL V
- 4. ENEA
- 5. SSTC-NRS
- 6. ARB
- 7. BOKU
- 8. EK
- 9. UJV
- 10. HZDR
- 11. CIEMAT
- 12. LEI
- 13. JRC
- 14. TRACTEBEL
Description
This report covers the current capabilities of the available codes that will be used within the R2CA H2020 project in the release evaluation methodologies of LOCA and SGTR transients in different kinds of reactors (PWRs, VVERs, EPR, BWR) displaying both code descriptions and model comparison tables. It includes both system codes and codes focusing on a part of the phenomenology only, in particular focusing on the determination of the fuel rod failures as well as on the consequences of these failures. A state of the art of the combined use of these codes in implementation of the release evaluation methodologies is also described. The work that has been done covers fuel performance, sub-channel and system thermal-hydraulics, radionuclide transport and integral system behaviour. Codes modelling only the steady-state operation (especially fuel codes) have also been included as they produce initial conditions for the transient codes and are integral part of the calculation chains. Finally, the developments items for the codes, that will be addressed within the R2CA project, are also summarized dealing with cladding modelling, fuel and fission product modelling, code coupling and whole core modelling and nodalization.
Files
R2CA D2.2 simulation code review.pdf
Files
(4.5 MB)
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