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Study on corrosion model and experimental verification of CuCrZr alloy for fusion reactor
NUCLEAR ENERGY SCIENCE AND ENGINEERING | 更新时间：2024-10-25
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    • Study on corrosion model and experimental verification of CuCrZr alloy for fusion reactor

    • “In the field of material research for the water cooling circuit of fusion reactor filters, experts have constructed a CuCrZr alloy corrosion model to provide scientific basis for the calculation of radioactive source terms. The maximum relative error between the calculated values of the model and the experimental values is 12.1%.”
    • NUCLEAR TECHNIQUES   Vol. 43, Issue 11, (2020)

    • DOI：10.11889/j.0253-3219.2020.hjs.43.110602    

      CLC： TL99

    • Received：02 June 2020，

      Revised：03 July 2020，

      Published：15 November 2020

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  • ZHU Huiping,LIU Xudong,CHEN Jiawei,et al.Study on corrosion model and experimental verification of CuCrZr alloy for fusion reactor[J].NUCLEAR TECHNIQUES,2020,43(11):76-82. DOI： 10.11889/j.0253-3219.2020.hjs.43.110602.

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