Characteristics of 3D Printed Functionally Graded Material for Replacement of Dissimilar Metal Weld in Nuclear Reactor

• Autorzy: Yoon Ji-Hyun , Kim Jeoung Han

Identyfikatory

DOI

10.24425/amm.2024.147782

• Języki publikacji: EN

Abstrakty

EN

The dissimilar metal welds in the most of the reactors are connections between low alloy steel parts and stainless steel piping. There is a high possibility of primary water stress corrosion cracking (PWSCC) damage attributed to residual stress caused by the difference in material properties in the dissimilar metal weld joints. A number of accidents such as leakage of radioactive coolant due to PWSCC have been reported around the world, posing a great threat to nuclear safety. The objective of this study is to develop a technology that can fundamentally remove dissimilar metal welds by replacing the existing dissimilar metal parts with the functionally graded material (FGM) manufactured by metal 3D printing consisting of low alloy steel and austenitic stainless steel. A powder production, mixing ratio calculation, and metal 3D printing were performed to fabricate the low alloy steel-stainless steel FGM, and microstructure analysis, mechanical properties, and coefficient of thermal expansion (CTE) measurement of the FGM were performed. As a result, it is observed that CTE tended to increase as the austenite content increased in FGM. The gradual change of coefficient of thermal expansion in a FGM showed that the additive manufacturing using 3D printing was effective for preventing an abrupt change in thermal expansion properties throughout their layers.

Słowa kluczowe

EN

functionally graded material; FGM; PWSCC; 3D printing; reactor; coefficient of thermal expansion; CTE

• Wydawca: Institute of Metallurgy and Materials Science of Polish Academy of Sciences ; Committee of Materials Engineering and Metallurgy of Polish Academy of Sciences
• Czasopismo: Archives of Metallurgy and Materials
• Rocznik: 2024
• Tom: Vol. 69, iss. 1
• Strony: 45--48
• Opis fizyczny: Bibliogr. 11 poz., fot., rys.

Twórcy

autor

Yoon Ji-Hyun

• Korea Atomic Energy Research Institute, Daejeon, South Korea

• https://orcid.org/0009-0007-2902-3520

autor

Kim Jeoung Han

• Hanbat National University, Daejeon, South Korea

• https://orcid.org/0000-0002-8439-0100

Bibliografia

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• [7] ASTM International, Standard Test Methods for Tension Testing of Metallic Materials, PA, USA (2022).
• [8] J.H. Yoon et al., Development of Advanced Joining and Performance Prediction Technologies for Structural Materials of Nuclear Systems. Korea Atomic Energy Research Institute Report, KAERI/RR-4799/2021 (2021).
• [9] P. Marshall, Short-Term Mechanical Properties, Austenitic Stainless Steel: Microstructure and Mechanical Properties, New York (1984).
• [10] A. Joseph, Sanjai K. Rai, T. Jayakumar, N. Murugan, Internation Journal of Pressure Vessels and Piping 82 (9), 700-705 (2005).
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Uwagi

This achievement is a research conducted with the support of the National Research Foundation of Korea with funding from the Ministry of Science and ICT (NRF-2017M2A8A0143).