Zobrazeno 1 - 10
of 83
pro vyhledávání: '"Mark Kirk"'
Publikováno v:
Metals, Vol 13, Iss 1, p 176 (2023)
The use of mini-CT specimens for the fracture characterization of structural steels is currently a topic of great interest from both scientific and technical points of view, mainly driven by the needs and requirements of the nuclear industry. In fact
Externí odkaz:
https://doaj.org/article/17bb256283b04ce1a9703ed3bf2674f6
Publikováno v:
Metals, Vol 12, Iss 3, p 481 (2022)
The standard ASTM E900-15 provides an analytical expression to determine the transition temperature shift exhibited by Charpy V-notch data at 41-J for irradiated pressure vessel materials as a function of the variables copper, nickel, phosphorus, man
Externí odkaz:
https://doaj.org/article/f4bb459973e14175937e6f5d52bca6ce
Publikováno v:
Metals, Vol 12, Iss 2, p 186 (2022)
The long-term operating strategy of nuclear plants must ensure the integrity of the vessel, which is subjected to neutron irradiation, causing its embrittlement over time. Embrittlement trend curves used to predict the dependence of the Charpy transi
Externí odkaz:
https://doaj.org/article/6e9a777afb1f490f8c4e04140ed88e1e
Autor:
MARK KIRK
Publikováno v:
Nuclear Engineering and Technology, Vol 45, Iss 3, Pp 277-294 (2013)
In the early 1980s, attention focused on the possibility that pressurized thermal shock (PTS) events could challenge the integrity of a nuclear reactor pressure vessel (RPV) because operational experience suggested that overcooling events, while not
Externí odkaz:
https://doaj.org/article/77cb96cb09074c7eae703dca9018db8f
Publikováno v:
Volume 1: Codes and Standards.
The use of 4 mm thickness Mini-C(T) specimens for Master Curve evaluation is drawing attention as a possible alternative / supplemental surveillance test method to current Charpy-based approaches in on-going efforts to update JEAC4201[1]. Obtaining a
Publikováno v:
Volume 1: Codes and Standards.
The Master Curve and its index temperature To have, over the last three decades, gained more and more acceptance in Codes, Standards, and the regulatory frameworks of different countries. For example, the Japanese Electric Association Code (JEAC) 420
Publikováno v:
Volume 1: Codes and Standards.
A companion paper presented at this conference summarizes a recently published EPRI report that provides a Technical Basis for Code Case N-914, “Accounting for the Effect of Embrittlement on Fracture Toughness Properties Used in Evaluations of Pres
Publikováno v:
Volume 1: Codes and Standards.
Section XI of the ASME Boiler and Pressure Vessel Code includes methods to analyze the continued operating safety of nuclear power plant components. For the reactor pressure vessel (RPV) a means to account for the effects of neutron irradiation embri
Publikováno v:
Volume 1: Codes and Standards.
The ASME Section XI Working Group on Flaw Evaluation (WGFE) has an ongoing effort intended to implement the KJc Master Curve (MC), as defined in ASTM E1921, into Section XI of the ASME Code. Code Case (CC) N-830 was approved by ASME in 2014 and was t
Publikováno v:
Journal of Nuclear Materials. 568:153886