Engineering Mechanics

Proceedings Vol. 19 (2013)

ENGINEERING MECHANICS 2013

Copyright © 2013 Institute of Thermomechanics, Academy of Sciences of the Czech Republic, v.v.i., Prague

 

Demjančuková K., Pečínka L.
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Historically, the safety of nuclear power plants (NPPs) is based on the ability to eliminate the large loss-of-coolant accident (large LOCA) which is represented by the double ended guillotine break of the primary circuit piping. As a matter of experience with operation of many nuclear units, US NRC prepared the so- called redefinition of large LOCA which is based on the theory of transition break size (TBS). For the PWR (Pressurized Water Reactor) the TBS is characterized by the piping with diameter of 360 mm. The regulatory body has to prove that the postulated circumferential crack satisfies the requirements of ASME Code, Section XI. In the paper a numerical example will be presented.

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