Overview of EPRI Long Term Operations Work on Nuclear Power Plant Concrete Structures

  • Joe WallEmail author
  • Sam Johnson
Conference paper
Part of the The Minerals, Metals & Materials Series book series (MMMS)


The Electric Power Research Institute (EPRI) has been engaged in collaborative research and development activities related to concrete in nuclear applications over the past several years in concert with the nuclear generation industry, foreign and domestic national laboratories and regulatory bodies and universities. The EPRI Long Term Operations program is focused on performing research activities that will help the industry extend operation beyond the first period of license renewal, which for US plants means operation beyond 60 years. In this overview talk, three subjects will be addressed—radiation damage in boiling and pressurized water reactor concrete biological shields, boric acid attack of pressurized water reactor spent fuel pool concrete substructures and alkali-silica reaction degradation of concrete structures. The results of these and other studies are expected to support utilities as they demonstrate technical bases to regulatory bodies for long term operation of commercial nuclear plants.


Concrete irradiation damage Spent fuel pool leakage Alkali silica reaction Concrete degradation 


  1. 1.
    H. Graves, Y. LePape, D.J. Naus, J. Rashid, V. Saouma, A. Sheikh, J.J. Wall, Expanded Materials Degradation Assessment–Volume 4: Aging of Concrete and Civil Structures, NUREG/CR-7153( 2014)Google Scholar
  2. 2.
    H. Hilsdorf, J. Kropp and H. Koch, “The Effects of Nuclear Radiation on the Mechanical Properties of Concrete”, American Concrete Institute Report SP-55-10 223–254 (1978)Google Scholar
  3. 3.
    K. Field, I. Remec, Y. LePape, Radiation effects in concrete for nuclear power plants – Part I: Quantification of radiation exposure and radiation effects. Nucl. Eng. Des. 282, 126–143 (2015)CrossRefGoogle Scholar
  4. 4.
    Y. LePape, K. Field, I. Remec, Radiation Effects in Concrete for Nuclear Power Plants – Part II: Perspective from Micromechanical Modeling. Nucl. Eng. Des. 282, 144–157 (2015)CrossRefGoogle Scholar
  5. 5.
    Expected Condition of Reactor Cavity Concrete after 80 Years of Radiation Exposure, EPRI Report 3002002676 (2014)Google Scholar
  6. 6.
    Structural Disposition of Neutron Radiation Exposure in BWR Vessel Support Pedestals, EPRI Report 3002008128 (2016)Google Scholar
  7. 7.
    US Nuclear Regulatory Commission, “Standard Review Plan for Review of Subsequent License Renewal Applications for Nuclear Power Plants”, NUREG-2192 (2016)Google Scholar
  8. 8.
    Long Term Operations: Impact of Radiation Heating on PWR Biological Shield Concrete, EPRI Report 3002008129 (2016)Google Scholar
  9. 9.
    American Concrete Institute, “Code Requirements for Nuclear Safety-Related Concrete Structures and Commentary”, ACI 349-13 (2014)Google Scholar
  10. 10.
    Structural Model for PWR Reactor Pressure Vessel Supports—Effects of Chronic Radiation Exposure on Margin, EPRI Report 3002007347 (2016)Google Scholar
  11. 11.
    W. S. Lapay, C.Y. Yang, C. Kim, “License Renewal Evaluation: Aging Management for Reactor Coolant System Supports”, Westinghouse Report WCAP-14422 (2000)Google Scholar
  12. 12.
    Aging Management for Leaking Spent Fuel Pools”, EPRI Report 3002007348 (2016)Google Scholar
  13. 13.
    Tools for Early Detection of ASR in Concrete Structures EPRI Report 3002005389 (2015)Google Scholar
  14. 14.
    Long-Term Operations: Cracking-Index Criteria for Alkali Silica-Reaction Affected Structure EPRI Report 3002008117 (2016)Google Scholar
  15. 15.
    Structural Deformation as a Result of Expansion from Alkali Silica Reaction EPRI Report 3002007595 (2016)Google Scholar

Copyright information

© The Minerals, Metals & Materials Society 2019

Authors and Affiliations

  1. 1.Nuclear Sector, Electric Power Research InstituteCharlotteUSA
  2. 2.G.W. Woodruff School of Mechanical EngineeringGeorgia Institute of TechnologyAtlantaUSA

Personalised recommendations