Chapter 43
PWR Reactor Vessel Integrity and Internals Aging Management


Chapter 43, authored by Timothy J. Griesbach, covers PWR Reactor Vessel Integrity and the ASME Boiler and Pressure Vessel Code. The authors's objective is to provide an overview of the codes and regulations for prevention of brittle fracture of reactor pressure vessels. The background and bases for the original Section III, Appendix G Code requirements are discussed along with a description of the recent improvements that have been implemented in the Code in Section XI, Appendix G using more up-to-date technology. The changes and improvements are detailed such as the method for determining stress intensity factors, structural factors to account for uncertainties in the analytical methods, and material reference toughness curves. While the Code has incorporated these technical changes, the philosophy of protecting the vessel against brittle fracture has remained the same. The chapter also discusses ongoing efforts to incorporate the Master Curve approach for vessel toughness into the ASME Code, it considers areas for future improvements in the Code method for brittle fracture prevention of PWR reactor vessels, and it summarizes the aging management of PWR reactor vessel internals.

  • 43.1 Introduction
  • 43.2 Codes and Regulations for the Prevention of Brittle Fracture
  • 43.3 Reference Toughness Curves
  • 43.4 Margin Studies for Operating P-T Limits
  • 43.5 Areas for Future Improvements to Section XI, Appendix G
  • 43.6 Aging Management of PWR Vessel Internals
  • 43.7 References

Related Content

Customize your page view by dragging and repositioning the boxes below.

Related Journal Articles
Related eBook Content
Topic Collections

Sorry! You do not have access to this content. For assistance or to subscribe, please contact us:

  • TELEPHONE: 1-800-843-2763 (Toll-free in the USA)
  • EMAIL: asmedigitalcollection@asme.org
Sign In