A probabilistic fracture mechanics model for the tubing degradation of the Koeberg steam generators

dc.contributor.advisorTait, Robert Ben_ZA
dc.contributor.authorDamon, Randolphen_ZA
dc.date.accessioned2014-07-31T11:30:31Z
dc.date.available2014-07-31T11:30:31Z
dc.date.issued2004en_ZA
dc.descriptionIncludes bibliographical references (leaves 115-124).
dc.description.abstractThe susceptibility of Steam Generator (SG) Tubes (particularly tubes manufactured from Inconel 600) to primary water stress corrosion cracking (PWSCC) has been a major concern to the nuclear industry since 1971, when this phenomenon was first observed outside the laboratory. Since the susceptibility of Inconel 600 to PWSCC in pure water was first established as a certainty, various electricity utilities have devoted considerable resources to determining the exact nature of this degradation phenomenon and to predicting its consequences. Whereas, the study of the nature of this degradation mechanism has led to many conflicting conclusions, the predictive methods developed have been more successful. Initially, the establishment of the Leak Before Risk of Break principle has allowed various utilities to justify SG operation with cracked tubes. Later, the development of probabilistic simulation methods, most notably by EdF and the Jozef Stefan Institute (JSI), have led to further justification of the existing maintenance regimes and also allowed the ability to do sensitivity studies with regards to various influencing parameters. The current maintenance regime at the Koeberg Nuclear Power Station (near Cape Town, South Africa) utilises tube plugging (when cracks exceed a certain length limit) and online leak detection (based on detection of radioactive Nitrogen 16) as the main means of ensuring safe SG operation. However, the plugging limit used is based on a conservative deterministic analysis, which may be penalising in some situations. Thus, the need for risk-based SG life-time optimisation was evident.en_ZA
dc.identifier.apacitationDamon, R. (2004). <i>A probabilistic fracture mechanics model for the tubing degradation of the Koeberg steam generators</i>. (Thesis). University of Cape Town ,Faculty of Engineering & the Built Environment ,Department of Mechanical Engineering. Retrieved from http://hdl.handle.net/11427/5571en_ZA
dc.identifier.chicagocitationDamon, Randolph. <i>"A probabilistic fracture mechanics model for the tubing degradation of the Koeberg steam generators."</i> Thesis., University of Cape Town ,Faculty of Engineering & the Built Environment ,Department of Mechanical Engineering, 2004. http://hdl.handle.net/11427/5571en_ZA
dc.identifier.citationDamon, R. 2004. A probabilistic fracture mechanics model for the tubing degradation of the Koeberg steam generators. University of Cape Town.en_ZA
dc.identifier.ris TY - Thesis / Dissertation AU - Damon, Randolph AB - The susceptibility of Steam Generator (SG) Tubes (particularly tubes manufactured from Inconel 600) to primary water stress corrosion cracking (PWSCC) has been a major concern to the nuclear industry since 1971, when this phenomenon was first observed outside the laboratory. Since the susceptibility of Inconel 600 to PWSCC in pure water was first established as a certainty, various electricity utilities have devoted considerable resources to determining the exact nature of this degradation phenomenon and to predicting its consequences. Whereas, the study of the nature of this degradation mechanism has led to many conflicting conclusions, the predictive methods developed have been more successful. Initially, the establishment of the Leak Before Risk of Break principle has allowed various utilities to justify SG operation with cracked tubes. Later, the development of probabilistic simulation methods, most notably by EdF and the Jozef Stefan Institute (JSI), have led to further justification of the existing maintenance regimes and also allowed the ability to do sensitivity studies with regards to various influencing parameters. The current maintenance regime at the Koeberg Nuclear Power Station (near Cape Town, South Africa) utilises tube plugging (when cracks exceed a certain length limit) and online leak detection (based on detection of radioactive Nitrogen 16) as the main means of ensuring safe SG operation. However, the plugging limit used is based on a conservative deterministic analysis, which may be penalising in some situations. Thus, the need for risk-based SG life-time optimisation was evident. DA - 2004 DB - OpenUCT DP - University of Cape Town LK - https://open.uct.ac.za PB - University of Cape Town PY - 2004 T1 - A probabilistic fracture mechanics model for the tubing degradation of the Koeberg steam generators TI - A probabilistic fracture mechanics model for the tubing degradation of the Koeberg steam generators UR - http://hdl.handle.net/11427/5571 ER - en_ZA
dc.identifier.urihttp://hdl.handle.net/11427/5571
dc.identifier.vancouvercitationDamon R. A probabilistic fracture mechanics model for the tubing degradation of the Koeberg steam generators. [Thesis]. University of Cape Town ,Faculty of Engineering & the Built Environment ,Department of Mechanical Engineering, 2004 [cited yyyy month dd]. Available from: http://hdl.handle.net/11427/5571en_ZA
dc.language.isoengen_ZA
dc.publisher.departmentDepartment of Mechanical Engineeringen_ZA
dc.publisher.facultyFaculty of Engineering and the Built Environment
dc.publisher.institutionUniversity of Cape Town
dc.subject.otherMechanical Engineeringen_ZA
dc.titleA probabilistic fracture mechanics model for the tubing degradation of the Koeberg steam generatorsen_ZA
dc.typeMaster Thesis
dc.type.qualificationlevelMasters
dc.type.qualificationnameMScen_ZA
uct.type.filetypeText
uct.type.filetypeImage
uct.type.publicationResearchen_ZA
uct.type.resourceThesisen_ZA
Files
Original bundle
Now showing 1 - 1 of 1
Loading...
Thumbnail Image
Name:
thesis_ebe_2004_damon_r (1).pdf
Size:
17.62 MB
Format:
Adobe Portable Document Format
Description:
Collections