Nuclear Engineering and Technology

  • 제56권11호
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  • Pages.4698-4707
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  • 2024
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  • 1738-5733(pISSN)
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  • 2234-358X(eISSN)
한국원자력학회 (Korean Nuclear Society)
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High-temperature material properties of type 316L stainless steel for the design of pressure boundary components subjected to 700℃ coolant

  • 투고 : 2024.03.14
  • 심사 : 2024.06.18
  • 발행 : 2024.11.25
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초록

The high-temperature material properties of Type 316L stainless steel (hereafter referred to as "316L SS") were determined through a series of material tests to enable the design of pressure vessels and piping operating up to 700 ℃. Currently, the only applicable design rule for 316L SS components in the high-temperature creep range is French high-temperature design standard, RCC-MRx. However, the material properties provided by RCC-MRx are limited to approximately 600 ℃. In this study, new material properties and relevant design coefficients for Type 316L components subjected to 700 ℃ coolant were determined based on material tests including tension, fatigue and creep tests conducted on 316L SS specimens. Utilizing these supplemented properties and design coefficients, the design of pressure boundary components and piping made of 316L SS in a large-scale test facility known as TESET, subjected to 700 ℃ coolant, was carried out. Several large-scale sodium tests at high temperatures up to 700 ℃ were successfully conducted at the TESET facility, with the main components and piping designed and constructed using 316L SS.

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과제정보

This work was supported by the National Research Council of Science & Technology (NST) grant (CAP20032-100) and the NRF grants (2021R1l1A2057941, 2021K1A3A1A78097845 and 2021M2E2A2081063) funded by the Korean government (MSIT). Technical assistances from Dr. Woo-Gon Kim of KETG and RCC-MRx Subcommittee are gratefully acknowledged.

참고문헌

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