Actions for Radiation Damage In Reactor Cavity Concrete [electronic resource].

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Radiation Damage In Reactor Cavity Concrete [electronic resource].

Published
Washington, D.C. : United States. Dept. of Energy, 2015.
Oak Ridge, Tenn. : Distributed by the Office of Scientific and Technical Information, U.S. Dept. of Energy
Physical Description
21-27 : digital, PDF file
Additional Creators
Oak Ridge National Laboratory, United States. Department of Energy, and United States. Department of Energy. Office of Scientific and Technical Information
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Summary
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.
Report Numbers
E 1.99:1201282
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Note
Published through SciTech Connect.
01/01/2015.
"RC0304000"
"NERC006"
Fontevraud 8 - Contribution of Materials Investigations and Operating Experience to LWRs Safety, Performance and Reliability, Avignon, France, 20140914, 20140919.
Field, Kevin G [ORNL]; Le Pape, Yann [ORNL]; Naus, Dan J [ORNL]; Remec, Igor [ORNL]; Busby, Jeremy T [ORNL]; Rosseel, Thomas M [ORNL]; Wall, Dr. James Joseph [Electric Power Research Institute (EPRI)].
Funding Information
AC05-00OR22725
View MARC record | catkey: 24470355