While risk-informed in-service inspection (RI-ISI) program has been applied in several countries to enhance the traditional periodic inspection program (PIP), many other countries are waiting for more successful implementation experiences to be accumulated. Canadian Nuclear Safety Commission (CNSC), the regulatory body of nuclear industry in Canada, became increasingly interested in the risk-informed decision making methodology. Several small-scale pilot studies on RI-ISI have been initiated by Canadian utilities during the past few years. Nevertheless, a RI-ISI methodology appropriate for the CANDU technology that can be accepted by the stakeholders has yet to be developed. The development of the RI-ISI methodologies derived from the PWR/BWR operating experiences is first reviewed, followed by an examination of Canadian periodic inspection standard CSA N285.4 and its evolution from a RI-ISI perspective. Finally several key technical issues and research needs in developing an advanced RI-ISI methodology for nuclear power plants are identified.
Skip Nav Destination
18th International Conference on Nuclear Engineering
May 17–21, 2010
Xi’an, China
Conference Sponsors:
- Nuclear Engineering Division
ISBN:
978-0-7918-4929-3
PROCEEDINGS PAPER
Advances and Research Needs in Risk-Informed In-Service Inspection Methodology Available to Purchase
X.-X. Yuan
X.-X. Yuan
Ryerson University, Toronto, ON, Canada
Search for other works by this author on:
X.-X. Yuan
Ryerson University, Toronto, ON, Canada
Paper No:
ICONE18-29608, pp. 187-194; 8 pages
Published Online:
April 8, 2011
Citation
Yuan, X. "Advances and Research Needs in Risk-Informed In-Service Inspection Methodology." Proceedings of the 18th International Conference on Nuclear Engineering. 18th International Conference on Nuclear Engineering: Volume 1. Xi’an, China. May 17–21, 2010. pp. 187-194. ASME. https://doi.org/10.1115/ICONE18-29608
Download citation file:
16
Views
Related Proceedings Papers
Related Articles
Pump and Valve Fastener Serviceability in PWR Nuclear Facilities
J. Pressure Vessel Technol (February,1996)
The Non-Nuclear Conversion of the Montalto BWR/6-Mark III Plant: A Technical and Economical Assessment of the Proposed Options
J. Energy Resour. Technol (June,1989)
The Fabulous Nuclear Odyssey of Belgium
J. Pressure Vessel Technol (June,2009)
Related Chapters
Iwe and Iwl
Companion Guide to the ASME Boiler and Pressure Vessel Code, Volume 2, Third Edition
IWE and IWL
Companion Guide to the ASME Boiler & Pressure Vessel Code, Volume 2, Second Edition: Criteria and Commentary on Select Aspects of the Boiler & Pressure Vessel and Piping Codes
IWE and IWL
Companion Guide to the ASME Boiler & Pressure Vessel Codes, Volume 2, Sixth Edition