• Title/Summary/Keyword: 소듐대 소듐 열교환기

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High-Temperature Design of Sodium-to-Air Heat Exchanger in Sodium Test Loop (소듐 시험루프 내 소듐대 공기 열교환기의 고온 설계)

  • Lee, Hyeong-Yeon;Eoh, Jae-Hyuk;Lee, Yong-Bum
    • Transactions of the Korean Society of Mechanical Engineers A
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    • v.37 no.5
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    • pp.665-671
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    • 2013
  • In a Korean Generation IV prototype sodium-cooled fast reactor (SFR), various types of high-temperature heat exchangers such as IHX (intermediate heat exchanger), DHX (decay heat exchanger), AHX (air heat exchanger), FHX (finned-tube sodium-to-air heat exchanger), and SG (steam generator) are to be designed and installed. In this study, the high-temperature design and integrity evaluation of the sodium-to-air heat exchanger AHX in the STELLA-1 (sodium integral effect test loop for safety simulation and assessment) test loop already installed at KAERI (Korea Atomic Energy Research Institute) and FHX in the SEFLA (sodium thermal-hydraulic experiment loop for finned-tube sodium-to-air heat exchanger) test loop to be installed at KAERI have been performed. Evaluations of creep-fatigue damage based on full 3D finite element analyses were conducted for the two heat exchangers according to the high-temperature design codes, and the integrity of the high-temperature design of the two heat exchangers was confirmed.

High-Temperature Design and Integrity Evaluation of Sodium-Cooled Fast Reactor Decay Heat Exchanger (소듐냉각고속로 붕괴열교환기의 고온 설계 및 건전성 평가)

  • Lee, Hyeong-Yeon;Eoh, Jae-Hyuk
    • Transactions of the Korean Society of Mechanical Engineers A
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    • v.37 no.10
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    • pp.1251-1259
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    • 2013
  • In this study, high temperature design and creep-fatigue damage evaluation of a decay heat exchanger (DHX) in the decay heat removal systems of a sodium-cooled fast reactor (SFR) have been performed. Detail design and 3D finite element analysis have been conducted for the DHXs to be installed in active and passive decay heat removal systems in Korean Generation IV SFR, and the DHX installed in the STELLA-1(Sodium integral effect test loop for safety simulation and assessment) at KAERI (Korea Atomic Energy Research Institute). Evaluations of creep-fatigue damage based on full 3D finite element analyses were conducted for the two Mod.9Cr-1Mo steel heat exchangers according to the elevated temperature design codes of ASME Section III Subsection NH and RCC-MR code. Code comparisons were made based on the creep-fatigue damage evaluation and issues on conservatisms of the design codes were discussed.