DocumentCode
3119996
Title
Heat removal possibilities of nuclear containments during a severe accident
Author
Lovasz, Liviusz ; Boros, Ildiko
Author_Institution
Budapest Univ. of Technol. & Econ., Budapest, Hungary
fYear
2013
fDate
6-8 June 2013
Firstpage
1
Lastpage
5
Abstract
After the accident in Fukushima the safety reviews of nuclear power plants showed several safety shortcomings. One of the identified problems is the long term depressurization of containment buildings, in case of a station blackout. A possible solution for the problem for VVER-440 type nuclear power plants was analyzed in the work: how heat exchangers placed in the containment can reduce the pressure. The analysis was made with the integral source term code ASTEC. To prove the effectiveness of heat exchangers, a containment model was built and different simulations - without heat exchangers or with heat exchanger installed at different locations inside the containment building - were run.. The plant specific parameters came from the Paks Nuclear Power Plant. The analysis proved the efficiency of heat exchangers for depressurization, but showed that their effect highly depends on the location they are built in.
Keywords
fission reactor accidents; fission reactor containment; heat exchangers; nuclear power stations; ASTEC; Fukushima; Paks Nuclear Power Plant; VVER-440 type nuclear power plants; containment buildings; containment model; heat exchangers; heat removal possibilities; integral source term code; long term depressurization; nuclear containments; plant specific parameters; safety reviews; safety shortcomings; station blackout; Heating;
fLanguage
English
Publisher
ieee
Conference_Titel
Energy (IYCE), 2013 4th International Youth Conference on
Conference_Location
Sio??fok
Type
conf
DOI
10.1109/IYCE.2013.6604167
Filename
6604167
Link To Document