Status of Prestressed Concrete Reactor Vessel (PCRV) experimental and analytical programs in the United States. [HTGR]

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Description

During the past decade, the Oak Ridge National Laboratory has been engaged in a comprehensive program of experimental and analytical studies pertaining to the design and development of PCRVs. The program has been directed primarily toward the gas-cooled reactor since it has remained the only reactor concept currently utilizing PCRVs. However, interest has developed recently in potential applications to coal conversion systems. The purpose of the paper is to review the background and scope of the PCRV Research and Development Program and to summarize the status of the current studies.

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Pages: 33

Creation Information

Callahan, J P & Dodge, W G January 1, 1977.

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Description

During the past decade, the Oak Ridge National Laboratory has been engaged in a comprehensive program of experimental and analytical studies pertaining to the design and development of PCRVs. The program has been directed primarily toward the gas-cooled reactor since it has remained the only reactor concept currently utilizing PCRVs. However, interest has developed recently in potential applications to coal conversion systems. The purpose of the paper is to review the background and scope of the PCRV Research and Development Program and to summarize the status of the current studies.

Physical Description

Pages: 33

Notes

Dep. NTIS, PC A03/MF A01.

Source

  • Seminar on HTGR safety technology, Upton, NY, USA, 15 Sep 1977

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  • Report No.: CONF-770929-12
  • Grant Number: W-7405-ENG-26
  • Office of Scientific & Technical Information Report Number: 5356559
  • Archival Resource Key: ark:/67531/metadc1074659

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Office of Scientific & Technical Information Technical Reports

Reports, articles and other documents harvested from the Office of Scientific and Technical Information.

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Creation Date

  • January 1, 1977

Added to The UNT Digital Library

  • Feb. 4, 2018, 10:51 a.m.

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  • March 23, 2018, 1:31 p.m.

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Callahan, J P & Dodge, W G. Status of Prestressed Concrete Reactor Vessel (PCRV) experimental and analytical programs in the United States. [HTGR], article, January 1, 1977; Tennessee. (digital.library.unt.edu/ark:/67531/metadc1074659/: accessed August 18, 2018), University of North Texas Libraries, Digital Library, digital.library.unt.edu; crediting UNT Libraries Government Documents Department.