2018
DOI: 10.3897/nucet.4.31889
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A technique for detection of WWER fuel failures by activity of Xe radionuclides during reactor operation

Abstract: Fuel failures during operation of Nuclear Power Plants (NPPs) may lead to substantial economic losses. Negative effects of reactor operation with leaking fuel in the core may be reduced if fuel failures are detected in due time of the cycle. At present time, the ratio of the normalized release rates of 131I and 134I is used to detect fuel failures in WWERs during steady state operation. However, based on the activity of iodine radionuclides, it is not always possible to detect the fuel failure. This … Show more

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Cited by 5 publications
(1 citation statement)
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“…In order to determine whether the fuel cladding is defective, either a chemical sampling approach from the let-down flow or the real-time online monitoring system is used to collect specific activities in the primary coolant. By analyzing the specific activities of FPs derived by sampling or online monitoring, fuel rod failures are discovered by various methodologies, such as the release-to-birth ratio method (Zanker, 1989), fitted escape rate coefficient method (Yamamoto and Morishita, 2015), and isotopic ratio method (Kalinichev et al, 2018;Li et al, 2017) (Qin et al, 2016). Generally, these strategies are developed in consideration of the FP release model or reactor operation experience.…”
Section: Introductionmentioning
confidence: 99%
“…In order to determine whether the fuel cladding is defective, either a chemical sampling approach from the let-down flow or the real-time online monitoring system is used to collect specific activities in the primary coolant. By analyzing the specific activities of FPs derived by sampling or online monitoring, fuel rod failures are discovered by various methodologies, such as the release-to-birth ratio method (Zanker, 1989), fitted escape rate coefficient method (Yamamoto and Morishita, 2015), and isotopic ratio method (Kalinichev et al, 2018;Li et al, 2017) (Qin et al, 2016). Generally, these strategies are developed in consideration of the FP release model or reactor operation experience.…”
Section: Introductionmentioning
confidence: 99%