A method, MIM (magnetic interrogation method), is proposed for nondestructive measurement of radiation damage of nuclear reactor pressure vessels. The method relies on good correlation between the levels of radiation-induced hardness change and magnetic coercivity change in pressure vessel steel. A part of the pressure vessel to be inspected is magnetized with two-pole magnetic yokes through the overlay clad of nonmagnetic stainless steel, and magnetic field distributions on the surface of overlay clad are measured in the vicinity of the poles of magnetic yokes. Then, the coercivity distribution in the direction of thickness in the pressure vessel steel is inversely estimated from the measured magnetic field distribution patterns with aid of static magnetic field analysis. The level of radiation damage such as hardness change is assessed with relation to the estimated coercivity distributions.
Skip Nav Destination
Article navigation
November 1996
Research Papers
A New Method of Nondestructive Measurement for Assessment of Material Degradation of Aged Reactor Pressure Vessels
K. Ara,
K. Ara
Head, Sensing Technology Laboratory, Japan Atomic Energy Research Institute, Tokai-mura, Naka-gun, Ibaraki-ken, 319-11 Japan
Search for other works by this author on:
N. Ebine,
N. Ebine
Reactor Component Reliability Laboratory, Japan Atomic Energy Research Institute, Tokai-mura, Naka-gun, Ibaraki-ken, 319-11 Japan
Search for other works by this author on:
N. Nakajima
N. Nakajima
Reactor Component Reliability Laboratory, Japan Atomic Energy Research Institute, Tokai-mura, Naka-gun, Ibaraki-ken, 319-11 Japan
Search for other works by this author on:
K. Ara
Head, Sensing Technology Laboratory, Japan Atomic Energy Research Institute, Tokai-mura, Naka-gun, Ibaraki-ken, 319-11 Japan
N. Ebine
Reactor Component Reliability Laboratory, Japan Atomic Energy Research Institute, Tokai-mura, Naka-gun, Ibaraki-ken, 319-11 Japan
N. Nakajima
Reactor Component Reliability Laboratory, Japan Atomic Energy Research Institute, Tokai-mura, Naka-gun, Ibaraki-ken, 319-11 Japan
J. Pressure Vessel Technol. Nov 1996, 118(4): 447-453 (7 pages)
Published Online: November 1, 1996
Article history
Received:
June 3, 1994
Revised:
February 15, 1996
Online:
February 11, 2008
Citation
Ara, K., Ebine, N., and Nakajima, N. (November 1, 1996). "A New Method of Nondestructive Measurement for Assessment of Material Degradation of Aged Reactor Pressure Vessels." ASME. J. Pressure Vessel Technol. November 1996; 118(4): 447–453. https://doi.org/10.1115/1.2842212
Download citation file:
Get Email Alerts
The Behavior of Elbow Elements at Pure Bending Applications Compared to Beam and Shell Element Models
J. Pressure Vessel Technol (February 2025)
Related Articles
Evaluation of Radiation Damage in Reactor Pressure Vessel Steel by Elastic-Plastic Fracture Mechanics
J. Eng. Mater. Technol (October,1981)
The Influence of Impurity-Defect Interactions on Radiation Hardening and Embrittlement
J. Eng. Mater. Technol (April,1979)
Uniform Internal Finishing of SUS304 Stainless Steel Bent Tube Using a Magnetic Abrasive Finishing Process
J. Manuf. Sci. Eng (August,2005)
Heavy Section Steel Plates for Reactor Pressure Vessels Produced by Basic Oxygen Process
J. Pressure Vessel Technol (May,1977)
Related Proceedings Papers
Related Chapters
Lessons Learned: NRC Experience
Continuing and Changing Priorities of the ASME Boiler & Pressure Vessel Codes and Standards
The Design of a New Bluetooth Adapter
International Conference on Advanced Computer Theory and Engineering, 5th (ICACTE 2012)
Subsection NG — Core Support Structures
Companion Guide to the ASME Boiler and Pressure Vessel Code, Volume 1, Third Edition