Research on Release Calculation of Fission Product from Defect Fuel Rod to Reactor Coolant
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摘要: 分析包壳破损情况下裂变产物从燃料芯块向冷却剂的释放机理,建立裂变产物从燃料芯块向冷却剂的释放量的计算模型;采用CPR1000机型的设计参数对燃料包壳破损率、包壳破损尺寸和燃耗开展敏感性分析,计算等效逃脱率系数并与AP1000设计控制文件中给出的逃脱率系数进行比较。结果表明,包壳破损尺寸对裂变产物释放的影响较大,燃耗和包壳破损率对裂变产物释放影响较小。在包壳破口尺寸为34μm时,采用建立的计算模型计算所得部分核素的等效逃脱率系数与AP1000设计控制文件中给出的逃脱率系数极为接近。Abstract: The calculation model was established according to the research on the release mechanism of fission product from defect fuel rod to reactor coolant. The sensitivity analysis was carried out for fuel rod defect rate, fuel rod defect size and burnup base on the design date of CPR1000 nuclear power plant, and the calculated equivalent escape rate was compared with the escape rate described in AP1000 design control document. The sensitivity analysis and comparison results show that the calculation model is sensitive for fuel rod defect size but not sensitive for fuel rod defect rate and burn up. The calculated equivalent escape rate of part nuclides is similar as the escape rate of AP1000 design control document base on the calculation model and the 34μm fuel rod defect size.
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Key words:
- Fuel rod defect /
- Fission product /
- Primary coolant
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