Radiation-induced degradation of concrete in NPPs

Igor Remec, Thomas M. Rosseel, Kevin G. Field, Yann Le Pape

Research output: Chapter in Book/Report/Conference proceedingConference contributionpeer-review

5 Scopus citations

Abstract

Nuclear power plant life extensions to 60 and potentially 80 years of operation have renewed interest in long-term material degradation. One material being considered is concrete. Swelling of aggregates driven by radiation-induced displacements of atoms is currently considered to be the most probable leading contributor to the radiation-induced degradation of concrete mechanical properties. In the biological shields of nuclear plants, atom displacements are dominated by neutron contributions while gamma-ray contributions are negligible. For several minerals that are common constituents of aggregates in concrete, it was shown that approximately 95 % of the displacement per atom is generated by neutrons with energies above 0.1 MeV. Neutrons with energies above 1 MeV contribute only approximately 20 % to 25 % to the displacement per atom. Therefore, if neutron fluence is used as the correlation parameter for the concrete degradation, the 0.1 MeV neutron energy cutoff should be used for the fluence. Based on the projected neutron fluence values (E > 0.1 MeV) in the concrete biological shields of the U.S. pressurized water reactor fleet and the available data on radiation effects on concrete, some decrease in mechanical properties of concrete cannot be ruled out during extended operation beyond 60 years.

Original languageEnglish
Title of host publicationReactor Dosimetry
Subtitle of host publication16th International Symposium
EditorsMary Helen Sparks, K. Russell DePriest, David W. Vehar
PublisherASTM International
Pages201-211
Number of pages11
ISBN (Electronic)9780803176614
DOIs
StatePublished - 2018
Event16th International Symposium on Reactor Dosimetry, ISRD 2017 - Santa Fe, United States
Duration: May 7 2017May 12 2017

Publication series

NameASTM Special Technical Publication
VolumeSTP 1608
ISSN (Print)0066-0558

Conference

Conference16th International Symposium on Reactor Dosimetry, ISRD 2017
Country/TerritoryUnited States
CitySanta Fe
Period05/7/1705/12/17

Funding

This manuscript has been authored by UT-Battelle, LLC, under contract DE-AC0500OR22725 with the U.S. Department of Energy. The United States Government retains a nonexclusive, paid-up, irrevocable, worldwide license to publish or reproduce the published form of this manuscript, or allow others to do so, for United States Government purposes Oak Ridge National Laboratory is managed by UT-Battelle, LLC, under contract DE-AC05-00OR22725 for the U.S. Department of Energy. This research was supported by the U.S. Department of Energy, Office of Nuclear Energy, Light Water Reactor Sustainability Program.

FundersFunder number
Office of Nuclear Energy, Light Water Reactor Sustainability Program
UT-BattelleDE-AC0500OR22725
U.S. Department of Energy

    Keywords

    • Atom displacements
    • Concrete
    • Degradation
    • Gamma rays
    • Neutron fluence
    • Radiation-induced volumetric expansion (RIVE)

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