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Analysis of the Technological Evolution of Materials Requirements Included in Reactor Pressure Vessel Manufacturing Codes

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Listed:
  • Alvaro Rodríguez-Prieto

    (Department of Manufacturing Engineering, Universidad Nacional de Educación a Distancia (UNED), 28040 Madrid, Spain)

  • Mariaenrica Frigione

    (Department of Engineering for Innovation, University of Salento, Prov. le Lecce-Monteroni, 73100 Lecce, Italy)

  • John Kickhofel

    (Apollo Plus, 7 Weineggstrasse, 8008 Zurich, Switzerland)

  • Ana M. Camacho

    (Department of Manufacturing Engineering, Universidad Nacional de Educación a Distancia (UNED), 28040 Madrid, Spain)

Abstract

The growth of green energy technologies within the frame of the 7th Sustainable Development Goal (SDG) along with the concern about climatic changes make nuclear energy an attractive choice for many countries to ensure energy security and sustainable development as well as to actively address environmental issues. Unlike nuclear equipment (immovable goods), which are often well-catalogued and analyzed, the design and manufacturing codes and their standardized materials specifications can be considered movable and intangible goods that have not been thoroughly studied based on a detailed evaluation of the scientific and technical literature on the reactor pressure vessel (RPV) materials behavior. The aim of this work is the analysis of historical advances in materials properties research and associated standardized design codes requirements. The analysis, based on the consolidated U.S. Nuclear Regulatory Commission (NRC) Regulatory Guide (RG) 1.99 Rev.2 model, enables determination of the best materials options, corresponding to some of the most widely used material specifications such as WWER 15Kh2MFAA (used from the 1970s and 1980s; already in operation), ASME SA-533 Grade B Cl.1 (used in pressurized water reactor-PWR 2nd–4th; already in operation), DIN 20MnMoNi55 and DIN 22NiMoCr37 (used in PWR 2nd–4th) as well as ASTM A-336 Grade F22V (current designs). Consequently, in view of the results obtained, it can be concluded that the best options correspond to recently developed or well-established specifications used in the design of pressurized water reactors. These assessments endorse the fact that nuclear technology is continually improving, with safety being its fundamental pillar. In the future, further research related to the technical heritage from the evolution of materials requirements for other clean and sustainable power generation technologies will be performed.

Suggested Citation

  • Alvaro Rodríguez-Prieto & Mariaenrica Frigione & John Kickhofel & Ana M. Camacho, 2021. "Analysis of the Technological Evolution of Materials Requirements Included in Reactor Pressure Vessel Manufacturing Codes," Sustainability, MDPI, vol. 13(10), pages 1-20, May.
    • Handle: RePEc:gam:jsusta:v:13:y:2021:i:10:p:5498-:d:554518
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    References listed on IDEAS

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    1. Kang-Heon Lee & Min-Gil Kim & Jeong Ik Lee & Phill-Seung Lee, 2015. "Recent Advances in Ocean Nuclear Power Plants," Energies, MDPI, vol. 8(10), pages 1-23, October.
    2. David M. Goldberg & Sukhwa Hong, 2019. "Minimizing the Risks of Highway Transport of Hazardous Materials," Sustainability, MDPI, vol. 11(22), pages 1-10, November.
    3. Jérôme Serp & Christophe Poinssot & Stéphane Bourg, 2017. "Assessment of the Anticipated Environmental Footprint of Future Nuclear Energy Systems. Evidence of the Beneficial Effect of Extensive Recycling," Energies, MDPI, vol. 10(9), pages 1-19, September.
    4. Andrea Di Ronco & Francesca Giacobbo & Guglielmo Lomonaco & Stefano Lorenzi & Xiang Wang & Antonio Cammi, 2020. "Preliminary Analysis and Design of the Energy Conversion System for the Molten Salt Fast Reactor," Sustainability, MDPI, vol. 12(24), pages 1-17, December.
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    Cited by:

    1. Alvaro Rodríguez-Prieto & Manuel Callejas & Ernesto Primera & Guglielmo Lomonaco & Ana María Camacho, 2022. "Multicriteria Analytical Model for Mechanical Integrity Prognostics of Reactor Pressure Vessels Manufactured from Forged and Rolled Steels," Mathematics, MDPI, vol. 10(10), pages 1-17, May.
    2. Alvaro Rodríguez-Prieto & Ana María Camacho & Carlos Mendoza & John Kickhofel & Guglielmo Lomonaco, 2021. "Evolution of Standardized Specifications on Materials, Manufacturing and In-Service Inspection of Nuclear Reactor Vessels," Sustainability, MDPI, vol. 13(19), pages 1-25, September.

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