A novel assessment of delayed neutron detector data in CANDU reactors

Aylward, Will and Wallace, Christopher and West, Graeme and McEwan, Curtis (2020) A novel assessment of delayed neutron detector data in CANDU reactors. Journal of Nuclear Engineering and Radiation Science, 6 (4). 041107. ISSN 2332-8983 (https://doi.org/10.1115/1.4046824)

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Abstract

A common opportunity for nuclear power plant operators is ensuring that routinely collected data is fully leveraged. Exploiting data analytics can enable improvements in anomaly detection and condition monitoring by identifying previously unseen data trends and correlations without major financial investment. One such opportunity is in facilitating the detection of fuel defects by augmenting the delayed neutron monitoring system deployed in the majority of CANDU reactors. In this paper we demonstrate using archive data that the detection of fuel defects can be accelerated using this system in combination with the use of a deeper historical dataset and the introduction of a smoothing algorithm. The current defect identification process relies on the analysis of data of high variance and is subject to the judgement of a domain expert, resulting in variable defect identification periods. The proposed approaches seek to mitigate this and alleviate the variable identification time. Initial results presented here show that for an initial batch of 30 defects, identification periods can be meaningfully reduced compared to the current process, with defects potentially visible an average of 11.4 days earlier. By shortening this identification period, fuel containing defects can be scheduled for earlier removal, reducing the risk of statutory shutdown obligations, protecting personnel and promoting industry best practice. Exploring a historical dataset identifies previously undocumented trends and we discuss the potential to produce correlations with other reactor parameters. The application of this knowledge can lead to opportunities in the use of machine learning algorithms and, ultimately, more accurate predictions.

ORCID iDs

Aylward, Will ORCID logoORCID: https://orcid.org/0000-0002-2216-1310, Wallace, Christopher, West, Graeme ORCID logoORCID: https://orcid.org/0000-0003-0884-6070 and McEwan, Curtis;
CORE (COnnecting REpositories)