Auto Sizing of CANDU Nuclear Reactor Fuel Channel Flaws from UT Scans

Author:

Hammad Issam1ORCID,Poloni Matthew2,Isherwood Andrew2,Simpson Ryan3ORCID

Affiliation:

1. The Department of Engineering Mathematics and Internetworking, Dalhousie University, Halifax, NS B3H 4R2, Canada

2. The Inspection Analysis Department, Ontario Power Generation (OPG), 777 Brock Rd., Pickering, ON L1W 4A7, Canada

3. The Engineering Department, Alithya Digital Technology, 1420 Bayly St., Pickering, ON L1W 3R3, Canada

Abstract

The inspection of nuclear power plants is an essential process that occurs during plant outages. During this process, various systems are inspected, including the reactor’s fuel channels to ensure that they are safe and reliable for the plant’s operation. The inspection of Canada Deuterium Uranium (CANDU®) reactor pressure tubes, which are the core component of the fuel channels and house the reactor fuel bundles, is performed using Ultrasonic Testing (UT). Based on the current process that is followed by Canadian nuclear operators, the UT scans are manually examined by analysts to locate, measure, and characterize pressure tube flaws. This paper proposes solutions for the auto-detection and sizing of pressure tube flaws using two deterministic algorithms, the first uses segmented linear regression, while the second uses the average time of flight (ToF) within ±σ of µ. When compared against a manual analysis stream, the linear regression algorithm and the average ToF achieved an average depth difference of 0.0180 mm and 0.0206 mm, respectively. These results are very close to the depth difference of 0.0156 mm when comparing two manual streams. Therefore, the proposed algorithms can be adopted in production, which can lead to significant cost savings in terms of time and labor.

Funder

Ontario Power Generation

Alithya Digital Technology Corporation in Pickering, ON, Canada

Publisher

MDPI AG

Subject

Electrical and Electronic Engineering,Biochemistry,Instrumentation,Atomic and Molecular Physics, and Optics,Analytical Chemistry

Reference23 articles.

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3. Duffey, R.B., and Hedge, K. (1999, January 19–23). Future CANDU reactor development. Proceedings of the 7th International Conference on Nuclear Engineering, Tokyo, Japan.

4. Enhanced CANDU reactor with heat upgrade for combined power and hydrogen production;Dincer;Int. J. Hydrogen Energy,2019

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