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Development and verification of transient analysis code of helical coil steam generator of high-temperature gas-cooled reactor based on all-implicit algorithm
NUCLEAR ENERGY SCIENCE AND ENGINEERING | 更新时间：2025-06-17

    • Development and verification of transient analysis code of helical coil steam generator of high-temperature gas-cooled reactor based on all-implicit algorithm

    • “The transient analysis program NUSOL-HTGRSG for high-temperature gas cooled reactor spiral tube steam generator has been successfully developed, which effectively predicts operating parameters and provides a new direction for thermal hydraulic research.”
    • NUCLEAR TECHNIQUES   Vol. 48, Issue 4, Article number: 040608(2025)

    • DOI：10.11889/j.0253-3219.2025.hjs.48.240029    

      CLC： TL99

    • Received：02 April 2024，

      Revised：14 October 2024，

      Published：15 April 2025

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  • LIU Wei,HU Shouyin,XU Liang,et al.Development and verification of transient analysis code of helical coil steam generator of high-temperature gas-cooled reactor based on all-implicit algorithm[J].NUCLEAR TECHNIQUES,2025,48(04):040608. DOI： 10.11889/j.0253-3219.2025.hjs.48.240029. CSTR： 32193.14.hjs.CN31-1342/TL.2025.48.240029.

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