ASTM Standards for Reactor Dosimetry and Pressure Vessel Surveillance

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Description

The ASTM standards provide guidance and instruction on how to field and interpret reactor dosimetry. They provide a roadmap towards understanding the current ''state-of-the-art'' in reactor dosimetry, as reflected by the technical community. The consensus basis to the ASTM standards assures the user of an unbiased presentation of technical procedures and interpretations of the measurements. Some insight into the types of standards and the way in which they are organized can assist one in using them in an expeditious manner. Two example are presented to help orient new users to the breadth and interrelationship between the ASTM nuclear metrology standards. ... continued below

Physical Description

8 p.

Creation Information

GRIFFIN, PATRICK J. September 14, 1999.

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This article is part of the collection entitled: Office of Scientific & Technical Information Technical Reports and was provided by UNT Libraries Government Documents Department to Digital Library, a digital repository hosted by the UNT Libraries. It has been viewed 27 times . More information about this article can be viewed below.

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  • Sandia National Laboratories
    Publisher Info: Sandia National Labs., Albuquerque, NM, and Livermore, CA (United States)
    Place of Publication: Albuquerque, New Mexico

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Description

The ASTM standards provide guidance and instruction on how to field and interpret reactor dosimetry. They provide a roadmap towards understanding the current ''state-of-the-art'' in reactor dosimetry, as reflected by the technical community. The consensus basis to the ASTM standards assures the user of an unbiased presentation of technical procedures and interpretations of the measurements. Some insight into the types of standards and the way in which they are organized can assist one in using them in an expeditious manner. Two example are presented to help orient new users to the breadth and interrelationship between the ASTM nuclear metrology standards. One example involves the testing of a new ''widget'' to verify the radiation hardness. The second example involves quantifying the radiation damage at a pressure vessel critical weld location through surveillance dosimetry and calculation.

Physical Description

8 p.

Notes

INIS; OSTI as DE00012715

Medium: P; Size: 8 pages

Source

  • Tenth International Symposium on Reactor Dosimetry, Osaka (JP), 09/12/1999--09/18/1999

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  • Report No.: SAND99-0468C
  • Grant Number: AC04-94AL85000
  • Office of Scientific & Technical Information Report Number: 12715
  • Archival Resource Key: ark:/67531/metadc623061

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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

  • September 14, 1999

Added to The UNT Digital Library

  • June 16, 2015, 7:43 a.m.

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  • April 11, 2017, 3:53 p.m.

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GRIFFIN, PATRICK J. ASTM Standards for Reactor Dosimetry and Pressure Vessel Surveillance, article, September 14, 1999; Albuquerque, New Mexico. (digital.library.unt.edu/ark:/67531/metadc623061/: accessed July 15, 2018), University of North Texas Libraries, Digital Library, digital.library.unt.edu; crediting UNT Libraries Government Documents Department.