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https://hdl.handle.net/11681/11403
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DC Field | Value | Language |
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dc.contributor | U.S. Atomic Energy Commission. | - |
dc.contributor.author | McDonald, J. E. (James E.) | - |
dc.date.accessioned | 2016-06-20T14:19:41Z | - |
dc.date.available | 2016-06-20T14:19:41Z | - |
dc.date.issued | 1970-10 | - |
dc.identifier.uri | http://hdl.handle.net/11681/11403 | - |
dc.description | Miscellaneous paper | - |
dc.description | Foreword: This paper was prepared for the American Concrete Institute (ACI) Seminar on Concrete for Nuclear Reactors, held at Berlin, Germany, on 4-11 October 1970. The manuscript was reviewed and cleared for presentation by the Oak Ridge National Laboratory and the Office, Chief of Engineers, U. S. Army. The study which provided the information and data discussed herein is being conducted by the U. S. Army Engineer Waterways Experiment Station (WES), Vicksburg, Miss., under the sponsorship of the U. S. Atomic Energy Commission. This continuing investigation was initiated in 1966. Staff members actively involved in the investigation include Mr. Bryant Mather, Chief of the WES Concrete Division, Mr. J. M. Polatty, Chief of the Engineering Mechanics Branch, Dr. H. G. Geymayer, former Chief of the Structures Section, and Dr. J. C. Chakrabarti. Mr. James E. McDonald, current project engineer for this investigation, prepared this paper. Directors of the WES during the conduct of this investigation and preparation of this paper were COL John R. Oswalt, Jr., CE; COL Levi A. Brown, CE; and COL Ernest D. Peixotto, CE. Technical Directors were Mr. J. B. Tiffany and Mr. F. R. Brown. | - |
dc.publisher | Concrete Laboratory (U.S.) | - |
dc.publisher | Engineer Research and Development Center (U.S.) | - |
dc.relation | http://acwc.sdp.sirsi.net/client/en_US/search/asset/1044476 | - |
dc.relation.ispartofseries | Miscellaneous paper (U.S. Army Engineer Waterways Experiment Station) ; C-70-20. | - |
dc.rights | Approved for public release; distribution is unlimited. | - |
dc.source | This Digtal Resource was created from scans of the Print Resource. | - |
dc.subject | Concrete | - |
dc.subject | Creep | - |
dc.subject | Prestressed concrete reactor vessel | - |
dc.title | An experimental study of multiaxial creep in concrete | - |
dc.type | Report | en_US |
Appears in Collections: | Miscellaneous Paper |
Files in This Item:
File | Description | Size | Format | |
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MP-C-70-20.pdf | 1.59 MB | Adobe PDF | ![]() View/Open |