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Sodium-cooled fast reactors (SFR) are primarily designed based on two high-temperature design codes: ASME Section III, Subsection 5 (ASME III-5) and RCC-MRx. ASME III-5 is a general high-temperature code applicable to various reactor types, but it lacks practical application experience in the United States. In contrast, RCC-MRx, a specialized code for sodium-cooled fast reactors, has accumulated extensive practical experience in France and has become an essential technical reference in this field. In the existing design codes, the use of allowable stress limits controls the stress levels in components, thereby limiting creep rupture and deformation. Due to the general nature of ASME III-5, its allowable stress limits are relatively simplified, and the stress evaluation process is more complex. On the other hand, RCC-MRx provides clearer definitions and methods for determining allowable stress limits, and its mechanical evaluation process is more straightforward. This paper compares and analyzes the allowable stress value rules and different levels of stress limit criteria in both codes, exploring their similarities and differences. Additionally, considering the specific requirements of domestic nuclear high-temperature equipment design, the paper proposes a suggested stress limit criterion for China's domestically developed Level 1 high-temperature components, offering recommendations for design engineers.

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Research on the Development of Load-Controlled Stress Limit Criteria for China-Specific Class 1 High-Temperature Component Design Codes

  • 会议论文

  • 发表日期：

    2026年

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  • Tao Luo,
  • Fuhai Gao,
  • Yafei Mo,
  • Lubo Wang

摘要

Sodium-cooled fast reactors (SFR) are primarily designed based on two high-temperature design codes: ASME Section III, Subsection 5 (ASME III-5) and RCC-MRx. ASME III-5 is a general high-temperature code applicable to various reactor types, but it lacks practical application experience in the United States. In contrast, RCC-MRx, a specialized code for sodium-cooled fast reactors, has accumulated extensive practical experience in France and has become an essential technical reference in this field. In the existing design codes, the use of allowable stress limits controls the stress levels in components, thereby limiting creep rupture and deformation. Due to the general nature of ASME III-5, its allowable stress limits are relatively simplified, and the stress evaluation process is more complex. On the other hand, RCC-MRx provides clearer definitions and methods for determining allowable stress limits, and its mechanical evaluation process is more straightforward. This paper compares and analyzes the allowable stress value rules and different levels of stress limit criteria in both codes, exploring their similarities and differences. Additionally, considering the specific requirements of domestic nuclear high-temperature equipment design, the paper proposes a suggested stress limit criterion for China's domestically developed Level 1 high-temperature components, offering recommendations for design engineers.