• NUCLEAR TECHNIQUES
  • Vol. 47, Issue 9, 090601 (2024)
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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    DOI: 10.11889/j.0253-3219.2024.hjs.47.090601 Cite this Article
    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 Copy Citation Text show less
    Geometry and meshing of a fuel rod
    Fig. 1. Geometry and meshing of a fuel rod
    Variation of average oxide thickness with burnup
    Fig. 2. Variation of average oxide thickness with burnup
    Test sample diagram
    Fig. 3. Test sample diagram
    Hydrogen distribution after 3.9 days
    Fig. 4. Hydrogen distribution after 3.9 days
    Hydrogen distribution after 30 days
    Fig. 5. Hydrogen distribution after 30 days
    Variation of hydrogen of Css (a), Cp (b) after 30 days
    Fig. 6. 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
    Fig. 7. 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)
    Fig. 8. Comparisons of BEEs predictions of α2 with that of BISON predictions and experimental results (color online)
    Diagram of geometry and meshing of the cladding
    Fig. 9. 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
    Fig. 10. 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
    Fig. 11. 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
    Fig. 12. Radial distribution of hydrogen along cladding after 1 620 days

    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 1. CABRI REP-Na10 rodlet simulation parameters
    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 2. Hydrogen distribution simulation parameters under high temperature gradient

    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
    Table 3. Gravelines nuclear power plant irradiation examination parameters
    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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