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Quantitative estimation of tritium content in graphite for thorium molten salt reactor
NUCLEAR ENERGY SCIENCE AND ENGINEERING | 更新时间：2025-10-15

    • Quantitative estimation of tritium content in graphite for thorium molten salt reactor

    • “In the field of nuclear energy, researchers have conducted experimental studies on the tritium content in thorium based molten salt reactor nuclear graphite, providing data support for the distribution and control of tritium in TMSR.”
    • NUCLEAR TECHNIQUES   Vol. 48, Issue 9, Article number: 090604(2025)

    • DOI：10.11889/j.0253-3219.2025.hjs.48.240209    

      CLC： TL941

    • Received：26 May 2024，

      Revised：2024-12-17，

      Published：15 September 2025

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  • ZENG Linlin,CHENG Wenyu,WANG Chenxu,et al.Quantitative estimation of tritium content in graphite for thorium molten salt reactor[J].NUCLEAR TECHNIQUES,2025,48(09):177-186. DOI： 10.11889/j.0253-3219.2025.hjs.48.240209. CSTR： 32193.14.hjs.CN31-1342/TL.2025.48.240209.

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ZENG Linlin1
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CHENG Wenyu1
WANG Chenxu1
LI Lei3
ZENG Youshi1
LIU Wenguan4
DENG Ke 1

Related Institution

1. Shanghai Institute of Applied Physics，Chinese Academy of Sciences
Shanghai Institute of Measurement and Testing Technology
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Shanghai Institute of Applied Physics, Chinese Academy of Sciences, Jiading Campus
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