Abstract
Capability of the MELCOR code to model the passive
containment cooling system of the GE Hitachi ESBWR
reactor design was investigated. The system consists of
vertical tubes immersed in a water pool. Steam from the
containment flows through the tubes and condenses on
their inner surfaces. Results from three test facilities
were utilized in the model development. In some cases
MELCOR underestimated the condensation rate significantly
when using default heat transfer parameters. This problem
was corrected by modifying the Reynolds number limits for
classifying the condensate film flow as laminar or
turbulent to values found in literature. After this
modification, it is possible to achieve better than 10 %
accuracy in the condensation rate. Also aerosol
deposition in the condenser tubes is reproduced well. In
order to avoid oscillation and excessively short time
steps, careful modeling of drainage of the condensed
water out of the condenser is important.
Original language | English |
---|---|
Title of host publication | 22nd International Conference Nuclear Energy for New Europe, NENE 2013 |
Place of Publication | Ljubljana |
Number of pages | 9 |
Publication status | Published - 2013 |
MoE publication type | A4 Article in a conference publication |
Event | 22nd International Conference Nuclear Energy for New Europe, NENE 2013 - Bled, Slovenia Duration: 9 Sept 2013 → 12 Sept 2013 |
Conference
Conference | 22nd International Conference Nuclear Energy for New Europe, NENE 2013 |
---|---|
Abbreviated title | NENE 2013 |
Country/Territory | Slovenia |
City | Bled |
Period | 9/09/13 → 12/09/13 |
Keywords
- nuclear safety
- severe accidents
- passive containment cooling system
- MELCOR