Zobrazeno 1 - 10
of 24
pro vyhledávání: '"Timothy J. Griesbach"'
Autor:
Aparna Alleshwaram, Timothy J. Griesbach, Dilip Dedhia, David O. Harris, Kyle Amberge, Nathaniel G. Cofie
Publikováno v:
Volume 1B: Codes and Standards.
ASME Code, Section XI Code Case N-838 provides analyses methods that may be used when performing flaw tolerance evaluation of Class 1 and 2 cast austenitic stainless steel (CASS) piping components with ferrite content exceeding 20%. Tolerable flaw si
Autor:
Kyle Amberge, Timothy J. Griesbach, Aparna Alleshwaram, Dilip Dedhia, Nathaniel G. Cofie, David O. Harris
Publikováno v:
Volume 1: Codes and Standards.
Thermal aging of cast austenitic stainless steel (CASS) piping is a concern for long-term operation of nuclear power plants. Traditional conservative deterministic fracture mechanics analyses lead to tolerable crack sizes well below the sizes that ar
Autor:
Gary L. Stevens, Hardayal S. Mehta, Joshua Kusnick, Mark Kirk, Michael L. Benson, Timothy J. Griesbach, Daniel Sommerville
Publikováno v:
Volume 1: Codes and Standards.
A previous PVP paper [1] identified suggested improvements to be made to ASME Code, Section XI, Nonmandatory Appendix G, “Fracture Toughness Criteria for Protection Against Failure” [2]. That paper also identified that the current version of Appe
Publikováno v:
Volume 1A: Codes and Standards.
Thermal aging of cast austenitic stainless steel (CASS) piping is a concern for long term operation of nuclear power plants. The effects of aging in susceptible (i.e., high delta ferrite) CASS piping and components must be managed through the license
Publikováno v:
Volume 1: Codes and Standards.
The concern of toughness reduction due to thermal embrittlement of cast austenitic stainless steel (CASS) piping is increasing as nuclear power plants age. Because of the large and variable grain size of the CASS materials, the ultrasonic inspection
Publikováno v:
Volume 1: Codes and Standards.
This paper is the second in a continuing series of papers to highlight additional bases and recommended improvements to Appendix G. In 2008, the authors prepared a paper that reviewed some of the original basis documents for Appendix G for calculatin
Publikováno v:
Volume 1: Codes and Standards.
Prolonged exposure of cast austenitic stainless steels (CASS) to reactor coolant operating temperatures has been shown to lead to some degree of thermal aging embrittlement (reduction in fracture toughness of the material as a function of time). The
Publikováno v:
Volume 7: Operations, Applications and Components.
This paper provides a historical perspective of the effects of cladding and the analyses techniques used to evaluate the integrity of an RPV subjected to pressurized thermal shock (PTS) transients. A summary of the specific requirements of the draft
Publikováno v:
Volume 1: Codes and Standards.
This paper reviews some of the original basis documents for ASME Section XI Nonmandatory Appendix G for calculating pressure-temperature (P-T) limits and recommends areas for improvement. The original Appendix G in Section XI of ASME Code was mainly
Publikováno v:
Storage Tank Integrity and Materials Evaluation.
Boiling Water Reactor (BWR) plants in the U.S. are designed with radiation surveillance programs. However, the surveillance materials in some plants do not necessarily represent the limiting plate and/or weld material of the reactor pressure vessel (