Accelerated Aging of Concrete Dry Cask Storage Systems for Nuclear Waste-Reference-Cited by-同舟云学术

Accelerated Aging of Concrete Dry Cask Storage Systems for Nuclear Waste

Published:2016-06-29 Issue:6 Volume:14 Page:299-310
ISSN:1346-8014
Container-title:Journal of Advanced Concrete Technology
language:en
Short-container-title:ACT

Author:

Attar Arezou¹,Gencturk Bora²,Hanifehzadeh Mohammad¹,Willam Kaspar¹

Affiliation:

1. Department of Civil and Environmental Engineering, University of Houston, Houston, Texas, USA.

2. Sonny Astani Department of Civil and Environmental Engineering, University of Southern California, Los Angeles, CA, USA.

Publisher

Japan Concrete Institute

Subject

General Materials Science,Building and Construction

Link

https://www.jstage.jst.go.jp/article/jact/14/6/14_299/_pdf

Reference53 articles.

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2. 2) Andrews, A., (2006). “Radioactive waste streams: Waste classification for disposal.” Report No. RL32163, Congressional Research Service (CRS), Report for Congress.

3. 3) Andrews, A., (2008). “Nuclear fuel reprocessing: U.S. Policy Development.” Report No. S22542, Congressional Research Service (CRS), The Library of Congress.

4. 4) ASTM, (2008). “Standard test method for time of setting of concrete mixtures by penetration pesistance.” ASTM C403/C403M-08, American Society for Testing of Materials (ASTM), West Conshohocken, PA.

5. 5) ASTM, (2009a). “Standard test method for corrosion potentials of uncoated reinforcing steel in concrete.” ASTM C876-09, American Society for Testing of Materials (ASTM), West Conshohocken, PA.

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