Metallurgical failure analysis of a BWR recirculation pump shaft |
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| Affiliation: | 1. Materials Project, CIEMAT, Avda. Complutense 22, 28040 Madrid, Spain;2. NUCLENOR, C/ Hernán Cortés 26, 39003 Santander, Spain;1. Institute of Materials Science and Engineering (WKK), TU Kaiserslautern, P.O. Box 3049, 67653 Kaiserslautern, Germany;2. Center for Structural Materials, State Materials Testing Institute Darmstadt (MPA), Chair and Institute for Materials Technology (IfW), Technische Universität Darmstadt, 64283 Darmstadt, Germany;1. School of Energy and Power Engineering, Beihang University, No.37 Xueyuan RD. Haidian Dist., Beijing 100191, China;2. Department of Aerospace and Mechanical Engineering, University of Southern California, Los Angeles, CA 90089, USA;3. Collaborative Innovation Center of Advanced Aero-Engine, No.37 Xueyuan RD. Haidian Dist., Beijing 100191, China;4. Beijing Key Laboratory of Aero-Engine Structure and Strength, No.37 Xueyuan RD. Haidian Dist., Beijing 100191, China;1. Faculty of Energy Technology, University of Maribor, Slomškov trg 15, 2000 Maribor, Slovenia;2. Erlangen Graduate School in Advanced Optical Technologies (SAOT) and Institute of Engineering Thermodynamics (LTT), Friedrich-Alexander-Universität Erlangen-Nürnberg (FAU), Am Weichselgarten 8, 91058 Erlangen, Germany;3. Faculty of Energy Technology, University of Maribor, Slomškov trg 15, 2000, Slovenia;1. School of Mechanical Engineering, Beijing Institute of Technology, Beijing 100081, China;2. The State Key Laboratory of Automotive Safety and Energy, Beijing 100084, China |
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| Abstract: | This paper presents the metallurgical analysis of a Recirculation Pump from a Nuclear Power Plant. The damaged component was the austenitic stainless steel shaft. As a result of a preliminary visual examination, some axial cracks were found in the threaded area of the shaft in the thermal barrier area. The analyses performed include liquid penetrant testing, metallography and deposits analysis. Based on the obtained results, it was concluded that the origin of the axial cracks was thermal fatigue caused by mixing of cold seal injection water and hot reactor coolant in the thermal barrier area. |
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