Analysis of events related to cracks and leaks in the reactor coolant pressure boundary

Ballesteros, A.; Radian, Sanda; Peinador, Miguel; Benoît, Zerger; Negri, Patrice; Wenke, Rainer

doi:10.1016/j.nucengdes.2014.05.014

Cited by 7 publications

(3 citation statements)

References 4 publications

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“…Figure 1 shows the methodology followed in this topical study. This methodology has been applied also in other studies with different topics undertaken by the European Clearinghouse [2,5,9,13].…”

Section: Methodsmentioning

confidence: 99%

Maintenance related events in nuclear power stations

Ballesteros¹,

Radian²,

Maqua³

et al. 2016

EiN

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Section: Methodsmentioning

confidence: 99%

Maintenance related events in nuclear power stations

Ballesteros¹,

Radian²,

Maqua³

et al. 2016

EiN

Self Cite

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“…Te primary and secondary systems of nuclear power plants consist of several pipes, valves, and equipment. Tus, accidents involving leakage of the reactor coolant under conditions of high temperature and pressure may occur owing to thinning of the pipes, fatigue damage due to vibration of equipment, and aging of nuclear power plants [1][2][3]. In 2008, in the Kori Nuclear Power Plant Unit 3, which was in its normal operational state, a leak occurred at the drain valve weld on the B side of the steam generator.…”

Section: Introductionmentioning

confidence: 99%

Steam-Jet Evaluation for Predicting Leakage Behavior and Interpretation of Experimental Verification

Choi¹,

Park²,

Kim

et al. 2023

Science and Technology of Nuclear Installations

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Owing to pipe thinning, fatigue damage, and aging, pipes, valves, and devices installed in the primary and secondary systems of nuclear power plants may leak high-temperature/high-pressure reactor coolant. Thus, a system must be developed to determine if the leakage is exceeding the operating limit of the nuclear power plant, thereby mitigating any loss of life or economic loss in such cases. In this study, a validated numerical analysis method was established to initially simulate the leakage behavior and subsequently to evaluate the small amount of leakage in the compartment. For this purpose, a vapor-jet collision test in the compartment and a vapor-jet test in the pipe were performed; numerical analysis was conducted, and comparative analysis was performed to verify the validity of the established method. The evaluation results suggested that the proposed numerical analysis method could optimally simulate the flow characteristics of the steam jet. Notably, compared to the existing evaluation method, the proposed approach simulated a more detailed behavior of the jet formed at the leakage point. In future research, the results of this study (data) will be used to inform the design of the second phase of the leak-capture system and will be served as the foundation for a performance-optimization study on the capture system.

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“…Early stage cracks are small in dimensions and are usually smaller than half of the ultrasound wavelength. Importance of NDT early detection of possible defects in a pipeline is especially visible in nuclear power plant industry [2].…”

Section: Introductionmentioning

confidence: 99%

Possibilities of Reliable Ultrasonic Detection of Subwavelength Pipework Cracks

Hrabar¹,

Petošić²,

Franček³

et al. 2022

joe

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An occurrence of cracks in pipework could lead to potentially very dangerous malfunction in some critical engineering systems such as power plants. There is a clear trend of replacing traditional manual testing with non-invasive in-situ methods that should detect crack formation in its early stage. Such as approach would enable replacing of unhealthy pipe components during the regular periodic outages. Ultrasonic testing is known to be a rather mature and reliable technology. However, it suffers from serious problems in detection of the cracks of subwavelength size. This paper attempts to soften aforementioned problems by investigating the influence of a duration of the unipolar excitation signal on the achieved resolution. In addition, the transducer input electricalimpedance of NDT transmitter was measured by using different excitation pulses and their levels and the results are compared with those obtained using traditional frequency sweeping method at low excitation levels. Finally, use of some advanced signal processing algorithms that might lead to the automatic detection of subwavelength voids, in scenarios with low signal-to-noise ratio, is discussed.

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Analysis of events related to cracks and leaks in the reactor coolant pressure boundary

Cited by 7 publications

References 4 publications

Maintenance related events in nuclear power stations

Maintenance related events in nuclear power stations

Steam-Jet Evaluation for Predicting Leakage Behavior and Interpretation of Experimental Verification

Possibilities of Reliable Ultrasonic Detection of Subwavelength Pipework Cracks

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