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Title: Radiation Damage In Reactor Cavity Concrete

Abstract

License renewal up to 60 years and the possibility of subsequent license renewal to 80 years has established a renewed focus on long-term aging of nuclear generating stations materials, and recently, on concrete. Large irreplaceable sections of most nuclear generating stations include concrete. The Expanded Materials Degradation Analysis (EMDA), jointly performed by the Department of Energy, the Nuclear Regulatory Commission and Industry, identified the urgent need to develop a consistent knowledge base on irradiation effects in concrete. Much of the historical mechanical performance data of irradiated concrete does not accurately reflect typical radiation conditions in NPPs or conditions out to 60 or 80 years of radiation exposure. To address these potential gaps in the knowledge base, The Electric Power Research Institute and Oak Ridge National Laboratory are working to disposition radiation damage as a degradation mechanism. This paper outlines the research program within this pathway including: (i) defining the upper bound of the neutron and gamma dose levels expected in the biological shield concrete for extended operation (80 years of operation and beyond), (ii) determining the effects of neutron and gamma irradiation as well as extended time at temperature on concrete, (iii) evaluating opportunities to irradiate prototypical concrete under acceleratedmore » neutron and gamma dose levels to establish a conservative bound and share data obtained from different flux, temperature, and fluence levels, (iv) evaluating opportunities to harvest and test irradiated concrete from international NPPs, (v) developing cooperative test programs to improve confidence in the results from the various concretes and research reactors, (vi) furthering the understanding of the effects of radiation on concrete (see companion paper) and (vii) establishing an international collaborative research and information exchange effort to leverage capabilities and knowledge.« less

Authors:
 [1];  [1];  [1];  [1];  [1];  [1];  [2]
  1. ORNL
  2. Electric Power Research Institute (EPRI)
Publication Date:
Research Org.:
Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States)
Sponsoring Org.:
USDOE
OSTI Identifier:
1201282
DOE Contract Number:
AC05-00OR22725
Resource Type:
Conference
Resource Relation:
Conference: Fontevraud 8 - Contribution of Materials Investigations and Operating Experience to LWRs Safety, Performance and Reliability, Avignon, France, 20140914, 20140919
Country of Publication:
United States
Language:
English
Subject:
36 MATERIALS SCIENCE; 21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS; Radiation Effects; Concrete; Reactor

Citation Formats

Field, Kevin G, Le Pape, Yann, Naus, Dan J, Remec, Igor, Busby, Jeremy T, Rosseel, Thomas M, and Wall, Dr. James Joseph. Radiation Damage In Reactor Cavity Concrete. United States: N. p., 2015. Web.
Field, Kevin G, Le Pape, Yann, Naus, Dan J, Remec, Igor, Busby, Jeremy T, Rosseel, Thomas M, & Wall, Dr. James Joseph. Radiation Damage In Reactor Cavity Concrete. United States.
Field, Kevin G, Le Pape, Yann, Naus, Dan J, Remec, Igor, Busby, Jeremy T, Rosseel, Thomas M, and Wall, Dr. James Joseph. Thu . "Radiation Damage In Reactor Cavity Concrete". United States. doi:. https://www.osti.gov/servlets/purl/1201282.
@article{osti_1201282,
title = {Radiation Damage In Reactor Cavity Concrete},
author = {Field, Kevin G and Le Pape, Yann and Naus, Dan J and Remec, Igor and Busby, Jeremy T and Rosseel, Thomas M and Wall, Dr. James Joseph},
abstractNote = {License renewal up to 60 years and the possibility of subsequent license renewal to 80 years has established a renewed focus on long-term aging of nuclear generating stations materials, and recently, on concrete. Large irreplaceable sections of most nuclear generating stations include concrete. The Expanded Materials Degradation Analysis (EMDA), jointly performed by the Department of Energy, the Nuclear Regulatory Commission and Industry, identified the urgent need to develop a consistent knowledge base on irradiation effects in concrete. Much of the historical mechanical performance data of irradiated concrete does not accurately reflect typical radiation conditions in NPPs or conditions out to 60 or 80 years of radiation exposure. To address these potential gaps in the knowledge base, The Electric Power Research Institute and Oak Ridge National Laboratory are working to disposition radiation damage as a degradation mechanism. This paper outlines the research program within this pathway including: (i) defining the upper bound of the neutron and gamma dose levels expected in the biological shield concrete for extended operation (80 years of operation and beyond), (ii) determining the effects of neutron and gamma irradiation as well as extended time at temperature on concrete, (iii) evaluating opportunities to irradiate prototypical concrete under accelerated neutron and gamma dose levels to establish a conservative bound and share data obtained from different flux, temperature, and fluence levels, (iv) evaluating opportunities to harvest and test irradiated concrete from international NPPs, (v) developing cooperative test programs to improve confidence in the results from the various concretes and research reactors, (vi) furthering the understanding of the effects of radiation on concrete (see companion paper) and (vii) establishing an international collaborative research and information exchange effort to leverage capabilities and knowledge.},
doi = {},
journal = {},
number = ,
volume = ,
place = {United States},
year = {Thu Jan 01 00:00:00 EST 2015},
month = {Thu Jan 01 00:00:00 EST 2015}
}

Conference:
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