NUCLEAR TECHNIQUES, Volume. 48, Issue 7, 070020(2025)

Prediction method of reactor transient thermal-hydraulic parameters based on Seq2Seq model

Jingyu CHEN, Xiyang LIU, Tengwei YANG, Pengcheng ZHAO, and Zijing LIU*
Author Affiliations
  • School of Nuclear Science and Technology, University of South China, Hengyang 421001, China
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    References(19)

    [15] HAO Laomi, XIE Hui. DNBR calculation in the case of decrease in core coolant flow rate[J]. Atomic Energy Science and Technology, 27, 422-425(1993).

    [17] Gomez A, Jäger W, Sanchez V et al. On the influence of shape factors for CHF predictions with the sub channel code SUBCHANFLOW during a rod ejection[C](2012).

    [18] HU Peizheng. Study on multi-scale thermal-hydraulic coupling calculation method for reactor core[D](2019).

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    Jingyu CHEN, Xiyang LIU, Tengwei YANG, Pengcheng ZHAO, Zijing LIU. Prediction method of reactor transient thermal-hydraulic parameters based on Seq2Seq model[J]. NUCLEAR TECHNIQUES, 2025, 48(7): 070020

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    Paper Information

    Category: Special Issue on The First Academic Annual Conference of the Research Reactor and Innovative Reactor Association of Chinese Nuclear Society and Advanced Nuclear Power System Reactor Engineering

    Received: Apr. 21, 2024

    Accepted: --

    Published Online: Sep. 15, 2025

    The Author Email: Zijing LIU (LIUZijing)

    DOI:10.11889/j.0253-3219.2025.hjs.48.240132

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