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Reunderstand and Discuss the Hardness Limits of RCC-M M5110 Part Materials

Received: 23 February 2023    Accepted: 16 March 2023    Published: 24 March 2023
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Abstract

RCC-M M5110 is the procurement code for rolling or forging bars for bolts and drive rods of class 1, 2 and 3 equipment of nuclear power plants. The individual high strength steels involved in this specification specify only the minimum hardness of the material and have no limit on the maximum hardness. The material selection of major components of nuclear power machinery equipment must meet the requirements of load bearing and safe operation, and ensure sufficient strength and hardness, which is especially important for the material selection of connecting bolts and driving rods of nuclear power equipment. As the strength and hardness of high strength steel increase, the plasticity and toughness of materials decrease sharply, as do the mechanical properties and corrosion resistance, increasing the risk of bolt fracture and equipment damage. In order to ensure the strength and hardness of metal materials, it is necessary to consider the comprehensive mechanical properties and corrosion resistance of the material, including resistance stress corrosion cracking (SCC). Improving strength and hardness should not be the only goal of improving the performance of metal materials. In the formulation and selection of raw material standards, the mechanical properties of important equipment materials, such as hardness, must be limited. To meet the requirements of "redundant design" and "defense in depth" of nuclear power equipment. This paper will discuss how to reunderstand the the hardness limits of RCC-M M 5110 materials.

DOI 10.11648/j.ns.20230801.11
Published in Nuclear Science (Volume 8, Issue 1, March 2023)
Page(s) 1-7
Creative Commons

This is an Open Access article, distributed under the terms of the Creative Commons Attribution 4.0 International License (http://creativecommons.org/licenses/by/4.0/), which permits unrestricted use, distribution and reproduction in any medium or format, provided the original work is properly cited.

Copyright

Copyright © The Author(s), 2024. Published by Science Publishing Group

Keywords

RCC-M M5110, SCC, Bolt, Drive Rods, High Strength Steel, Hardness Limit

References
[1] RCC-M: Design and construction rules for mechanical components of nuclear island components French association for design, construction and in-service inspection rules for nuclear island components 2007.
[2] RCC-M M5110: RCC-M SECTION II MATERIALS 2007.
[3] ASTM-AIME, Symposium on Stress Corrosion cracking of Metals 1945.
[4] API 610: 2021/ISO13709: 2020 Centrifugal pumps for petroleum, petrochemical and natural gas industries.
[5] ANSI/NACE MR0103/ ISO17495-1: 2016 Petroleum, petrochemical and natural gas industries—Metallic materials resistant to sulfide stress cracking in corrosive petroleum refining environments.
[6] ANSI/NACE MR0175/ISO15156-1: 2015 Petroleum, petrochemical and natural gas industries—Materials for use in H2S-containing environments in oil and gas production— Part 1: General principles for selection of cracking-resistant materials.
[7] Li Xiao-gang chief Editor Introduction Corrosion and Protection of Materials (Second Edition) CHINA MACHINE PRESS 2017.
[8] Ji Gui chief Editor World Steel Number Control Manual China Standards Press 2007.
[9] Araki Toru, et. Editor Iron steel corrosion science Japan, Asakura Bookstore 1972.
[10] ASME: 2021 Boiler & Pressure Vessel Code II Materials Part A- Ferrous Material Specifications.
[11] ASME/ASTM SA-193/SA-193M Specification for Alloy-Steel and Stainless Steel Bolting Materials for High Temperature or High Pressure Service and Other Special Purpose Applications 2021.
[12] ASME SA354 Specification for Quenched and Tempered Alloy Steel Bolts, Studs, and Other Externally Threaded Fasteners 2021.
[13] Chinese national standard: GB/T3098.1-2010 Mechanical properties of fasteners- bolts, screws and studs.
[14] ASME/ASTM SA-705/SA-705M Specification for Age-Hardening Stainless Steel Forgings. 2021.
[15] ASME: 2021 Boiler & Pressure Vessel Code III Rules for Construction of Nuclear Facility Components.
[16] ZHANG Chen-li LI Jian-hua XU Liang Failure analysis of broken shaft of multistage centrifugal pump Petro-chemical Equipment 40 (3) 2019.
[17] GB/T16907-2014/ ISO9905 Technical specifications for centrifugal pumps - Class I.
[18] SHEN Yu-sheng LIU Yuan YAN Li-jun, How look at Exposed under Wet H2S Gas the Difference of pump Parts Material Strength Limit Value between Two Standard (GB/T16907 and API610) Pump technology (1) 2020.
Cite This Article
  • APA Style

    Shen Yu-sheng, Li Fang-zhong, Ma Wen-sheng, Zhou Jie, Zhao Xing-ying, et al. (2023). Reunderstand and Discuss the Hardness Limits of RCC-M M5110 Part Materials. Nuclear Science, 8(1), 1-7. https://doi.org/10.11648/j.ns.20230801.11

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    ACS Style

    Shen Yu-sheng; Li Fang-zhong; Ma Wen-sheng; Zhou Jie; Zhao Xing-ying, et al. Reunderstand and Discuss the Hardness Limits of RCC-M M5110 Part Materials. Nucl. Sci. 2023, 8(1), 1-7. doi: 10.11648/j.ns.20230801.11

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    AMA Style

    Shen Yu-sheng, Li Fang-zhong, Ma Wen-sheng, Zhou Jie, Zhao Xing-ying, et al. Reunderstand and Discuss the Hardness Limits of RCC-M M5110 Part Materials. Nucl Sci. 2023;8(1):1-7. doi: 10.11648/j.ns.20230801.11

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  • @article{10.11648/j.ns.20230801.11,
      author = {Shen Yu-sheng and Li Fang-zhong and Ma Wen-sheng and Zhou Jie and Zhao Xing-ying and Yan Li-jun},
      title = {Reunderstand and Discuss the Hardness Limits of RCC-M M5110 Part Materials},
      journal = {Nuclear Science},
      volume = {8},
      number = {1},
      pages = {1-7},
      doi = {10.11648/j.ns.20230801.11},
      url = {https://doi.org/10.11648/j.ns.20230801.11},
      eprint = {https://article.sciencepublishinggroup.com/pdf/10.11648.j.ns.20230801.11},
      abstract = {RCC-M M5110 is the procurement code for rolling or forging bars for bolts and drive rods of class 1, 2 and 3 equipment of nuclear power plants. The individual high strength steels involved in this specification specify only the minimum hardness of the material and have no limit on the maximum hardness. The material selection of major components of nuclear power machinery equipment must meet the requirements of load bearing and safe operation, and ensure sufficient strength and hardness, which is especially important for the material selection of connecting bolts and driving rods of nuclear power equipment. As the strength and hardness of high strength steel increase, the plasticity and toughness of materials decrease sharply, as do the mechanical properties and corrosion resistance, increasing the risk of bolt fracture and equipment damage. In order to ensure the strength and hardness of metal materials, it is necessary to consider the comprehensive mechanical properties and corrosion resistance of the material, including resistance stress corrosion cracking (SCC). Improving strength and hardness should not be the only goal of improving the performance of metal materials. In the formulation and selection of raw material standards, the mechanical properties of important equipment materials, such as hardness, must be limited. To meet the requirements of "redundant design" and "defense in depth" of nuclear power equipment. This paper will discuss how to reunderstand the the hardness limits of RCC-M M 5110 materials.},
     year = {2023}
    }
    

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  • TY  - JOUR
    T1  - Reunderstand and Discuss the Hardness Limits of RCC-M M5110 Part Materials
    AU  - Shen Yu-sheng
    AU  - Li Fang-zhong
    AU  - Ma Wen-sheng
    AU  - Zhou Jie
    AU  - Zhao Xing-ying
    AU  - Yan Li-jun
    Y1  - 2023/03/24
    PY  - 2023
    N1  - https://doi.org/10.11648/j.ns.20230801.11
    DO  - 10.11648/j.ns.20230801.11
    T2  - Nuclear Science
    JF  - Nuclear Science
    JO  - Nuclear Science
    SP  - 1
    EP  - 7
    PB  - Science Publishing Group
    SN  - 2640-4346
    UR  - https://doi.org/10.11648/j.ns.20230801.11
    AB  - RCC-M M5110 is the procurement code for rolling or forging bars for bolts and drive rods of class 1, 2 and 3 equipment of nuclear power plants. The individual high strength steels involved in this specification specify only the minimum hardness of the material and have no limit on the maximum hardness. The material selection of major components of nuclear power machinery equipment must meet the requirements of load bearing and safe operation, and ensure sufficient strength and hardness, which is especially important for the material selection of connecting bolts and driving rods of nuclear power equipment. As the strength and hardness of high strength steel increase, the plasticity and toughness of materials decrease sharply, as do the mechanical properties and corrosion resistance, increasing the risk of bolt fracture and equipment damage. In order to ensure the strength and hardness of metal materials, it is necessary to consider the comprehensive mechanical properties and corrosion resistance of the material, including resistance stress corrosion cracking (SCC). Improving strength and hardness should not be the only goal of improving the performance of metal materials. In the formulation and selection of raw material standards, the mechanical properties of important equipment materials, such as hardness, must be limited. To meet the requirements of "redundant design" and "defense in depth" of nuclear power equipment. This paper will discuss how to reunderstand the the hardness limits of RCC-M M 5110 materials.
    VL  - 8
    IS  - 1
    ER  - 

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Author Information
  • Chongqing Pump Industry Co, Ltd., Chongqing, China

  • Chongqing Pump Industry Co, Ltd., Chongqing, China

  • Chongqing Pump Industry Co, Ltd., Chongqing, China

  • Chongqing Pump Industry Co, Ltd., Chongqing, China

  • Chongqing Pump Industry Co, Ltd., Chongqing, China

  • Chongqing Pump Industry Co, Ltd., Chongqing, China

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