Stress analysis of 100-K primary piping

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Description

The program to assess the integrity of the K Reactor primary coolant piping systems with regard to the potential for brittle failure includes as an essential part an analysis of stresses in the piping materials both during normal operation and during emergency conditions. This program of stress analysis has recently been completed and has included the physical measurement of stress (strain) during normal operation, calculation of working stresses under design and actual conditions, and analysis of the probable effects on these stresses of emergency loadings. It is the intent of this report to present the results of the analysis of ... continued below

Physical Description

74 p.

Creation Information

Diediker, D. M. & Harrison, C. W. August 1969.

Context

This report 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. More information about this report can be viewed below.

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  • Douglas United Nuclear, Inc.
    Publisher Info: Douglas United Nuclear, Inc., Richland, WA (United States)
    Place of Publication: Richland, Washington

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Description

The program to assess the integrity of the K Reactor primary coolant piping systems with regard to the potential for brittle failure includes as an essential part an analysis of stresses in the piping materials both during normal operation and during emergency conditions. This program of stress analysis has recently been completed and has included the physical measurement of stress (strain) during normal operation, calculation of working stresses under design and actual conditions, and analysis of the probable effects on these stresses of emergency loadings. It is the intent of this report to present the results of the analysis of the measured and calculated stresses and to define to the extent possible the conditions of stress in the primary coolant piping systems during both normal and emergency conditions. The data is presented for further evaluation in conjunction with the results of the investigations being conducted to determined fracture toughness properties, crack growth rates, and nil ductility transition temperature ranges of the K Reactor coolant piping materials.

Physical Description

74 p.

Notes

OSTI as DE95015444

Source

  • Other Information: DN: Declassified

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Identifier

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  • Other: DE95015444
  • Report No.: DUN--5258
  • Grant Number: AC06-76RL01830
  • DOI: 10.2172/93597 | External Link
  • Office of Scientific & Technical Information Report Number: 93597
  • Archival Resource Key: ark:/67531/metadc794724

Collections

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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.

Office of Scientific and Technical Information (OSTI) is the Department of Energy (DOE) office that collects, preserves, and disseminates DOE-sponsored research and development (R&D) results that are the outcomes of R&D projects or other funded activities at DOE labs and facilities nationwide and grantees at universities and other institutions.

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Creation Date

  • August 1969

Added to The UNT Digital Library

  • Dec. 19, 2015, 7:14 p.m.

Description Last Updated

  • April 26, 2016, 2:11 p.m.

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Citations, Rights, Re-Use

Diediker, D. M. & Harrison, C. W. Stress analysis of 100-K primary piping, report, August 1969; Richland, Washington. (digital.library.unt.edu/ark:/67531/metadc794724/: accessed April 25, 2018), University of North Texas Libraries, Digital Library, digital.library.unt.edu; crediting UNT Libraries Government Documents Department.