NUCLEAR TECHNIQUES, Volume. 47, Issue 9, 090601(2024)

Development and validation of models for fuel rod oxidation and hydrogen pick-up behaviors in pressurized water reactor

Nan CHEN... Fengrui XIANG, Yanan HE*, Yingwei WU, Jing ZHANG, Guanghui SU, Wenxi TIAN and Suizheng QIU |Show fewer author(s)
Author Affiliations
  • Shaanxi Key Laboratory of Advanced Nuclear Energy and Technology, School of Nuclear Science and Technology, Xi'an Jiaotong University, Xi'an 710049, China
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    Figures & Tables(15)
    Geometry and meshing of a fuel rod
    Variation of average oxide thickness with burnup
    Test sample diagram
    Hydrogen distribution after 3.9 days
    Hydrogen distribution after 30 days
    Variation of hydrogen of Css (a), Cp (b) after 30 days
    Comparisons of BEEs predictions of precipitation temperature and hydrogen concentration with that of BISON predictions and TSSp
    Comparisons of BEEs predictions of α2 with that of BISON predictions and experimental results (color online)
    Diagram of geometry and meshing of the cladding
    Variation of cladding outside temperature (a) and linear power (b) with time in Gravelines nuclear power plant
    Variations of Css, TSSp (a), and Cp (b) with radial position after 1 620 days
    Radial distribution of hydrogen along cladding after 1 620 days
    • Table 1. CABRI REP-Na10 rodlet simulation parameters

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      Table 1. CABRI REP-Na10 rodlet simulation parameters

      设计参数

      Design parameters

      参数值

      Values

      包壳外径Cladding outer diameter / mm9.51
      包壳厚度Cladding thickness / mm0.575
      燃料外径Fuel pellet diameter / mm8.19
      燃料长度Fuel length / mm559
      充气压力Internal gas pressure / MPa0.301
      燃料包壳上端间隙Fuel-cladding top gap / mm32
      燃料包壳下端间隙Fuel-cladding bottom gap / mm3
      间隙宽度Fuel-cladding gap / mm0.082
    • Table 2. Hydrogen distribution simulation parameters under high temperature gradient

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      Table 2. Hydrogen distribution simulation parameters under high temperature gradient

      参数Parameters数值Values
      温度梯度Temperature gradient / K∙cm‒166
      冷端温度Cold end temperature / K589
      热端温度Hot end temperature / K756
      初始H浓度Initial H concentration / wt.ppm120
      样品初始温度Initial temperature / K300
      样品尺寸Sample size / cm2.5×0.025
    • Table 3. Gravelines nuclear power plant irradiation examination parameters

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      Table 3. Gravelines nuclear power plant irradiation examination parameters

      参数

      Parameters

      参数值

      Values

      包壳外径Cladding outer diameter / mm9.49
      包壳内径Cladding inner diameter / mm8.36
      冷却剂入口焓值Coolant inlet enthalpy / J∙g‒11 264
      冷却剂入口温度Coolant inlet temperature / ℃286
      冷却剂出口温度Coolant outlet temperature / ℃323
      燃料235U富集度Fuel enrichment / %4.5
      燃料平均燃耗Rod-averaged burnup / MWd∙tU‒158 230
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    Nan CHEN, Fengrui XIANG, Yanan HE, Yingwei WU, Jing ZHANG, Guanghui SU, Wenxi TIAN, Suizheng QIU. Development and validation of models for fuel rod oxidation and hydrogen pick-up behaviors in pressurized water reactor[J]. NUCLEAR TECHNIQUES, 2024, 47(9): 090601

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    Paper Information

    Category: NUCLEAR ENERGY SCIENCE AND ENGINEERING

    Received: Jan. 16, 2024

    Accepted: --

    Published Online: Nov. 13, 2024

    The Author Email:

    DOI:10.11889/j.0253-3219.2024.hjs.47.090601

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