12.07.2015 Views

applied fracture mechanics

applied fracture mechanics

applied fracture mechanics

SHOW MORE
SHOW LESS

You also want an ePaper? Increase the reach of your titles

YUMPU automatically turns print PDFs into web optimized ePapers that Google loves.

Chapter 9Methodology for Pressurized Thermal ShockAnalysis in Nuclear Power PlantDino A. Araneo and Francesco D’AuriaAdditional information is available at the end of the chapterhttp://dx.doi.org/10.5772/517531. IntroductionThe relevance of the <strong>fracture</strong> <strong>mechanics</strong> in the technology of the nuclear power plant ismainly connected to the risk of a catastrophic brittle rupture of the reactor pressure vessel.There are no feasible countermeasures that can mitigate the effects of such an event thatimpair the capability to maintain the core covered even in the case of properly functioningof the emergency systems.The origin of the problem is related to the aggressive environment in which the vesseloperates for long term (e.g. more than 40 years), characterized by high neutron flux duringnormal operation. Over time, the vessel steel becomes progressively more brittle in theregion adjacent to the core. If a vessel had a preexisting flaw of critical size and certainsevere system transients occurred, this flaw could propagate rapidly through the vessel,resulting in a through-wall crack. The severe transients that can lead the nuclear powerplant in such conditions, known as Pressurized Thermal Shock (PTS), are characterized byrapid cooling (i.e., thermal shock) of the a part of the internal reactor pressure vessel surfacethat may be combined with repressurization can create locally a sudden increase of thestresses inside the vessel wall and lead to the suddenly growth of the flaw inside the vesselthickness.Based on the long operational experience from nuclear power plants equipped with reactorpressure vessel all over the world, it is possible to conclude that the simultaneousoccurrence of critical-size flaws, embrittled vessel, and a severe PTS transient is a very lowprobability event. Moreover, additional studies performed at utilities and regulatoryauthorities levels have shown that the RPV can operate well beyond the original design life(40 years) because of the large safety margin adopted in the design phase.A better understanding and knowledge of the materials behavior, improvement insimulating in a more realistic way the plant systems and operational characteristics and a© 2012 Araneo and D’Auria, licensee InTech. This is an open access chapter distributed under the terms ofthe Creative Commons Attribution License (http://creativecommons.org/licenses/by/3.0), which permitsunrestricted use, distribution, and reproduction in any medium, provided the original work is properly cited.

Hooray! Your file is uploaded and ready to be published.

Saved successfully!

Ooh no, something went wrong!