This paper investigates the feasibility of increasing lithium concentration in the primary circuit system of CPR1000 nuclear power units in China. The methodology involves a comprehensive assessment encompassing multiple factors, including the impact on primary circuit materials, water quality, the influence of IASCC on stud bolt materials, and core fuel risk assessment. By analyzing these factors, the study aims to determine if extending the duration of peak lithium concentration can sustain a high pH level in the primary system throughout its operational lifetime, without causing any negative impacts on material corrosion, primary water stress corrosion cracking (PWSCC) susceptibility, intergranular stress corrosion cracking (IASCC) of stud bolts, or water quality.

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Elevated Lithium Concentration Effect on PWR Primary Materials

  • Zhang Yu,
  • Lin GenXian,
  • Liu Can Shuai,
  • Tian ZhaoHui,
  • Sun Yun

摘要

This paper investigates the feasibility of increasing lithium concentration in the primary circuit system of CPR1000 nuclear power units in China. The methodology involves a comprehensive assessment encompassing multiple factors, including the impact on primary circuit materials, water quality, the influence of IASCC on stud bolt materials, and core fuel risk assessment. By analyzing these factors, the study aims to determine if extending the duration of peak lithium concentration can sustain a high pH level in the primary system throughout its operational lifetime, without causing any negative impacts on material corrosion, primary water stress corrosion cracking (PWSCC) susceptibility, intergranular stress corrosion cracking (IASCC) of stud bolts, or water quality.