Predictability of steel containment response near failure

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Description

The Nuclear Power Engineering Corporation of Japan and the US Nuclear Regulatory Commission Office of Nuclear Regulatory Research, are co-sponsoring and jointly funding a Cooperative Containment Research Program at Sandia National Laboratories, Albuquerque, New Mexico, USA. As a part of this program, a steel containment vessel model and contact structure assembly was tested to failure with over pressurization at Sandia on December 11--12, 1996. The steel containment vessel model was a mixed-scale model (1:10 in geometry and 1:4 in shell thickness) of a steel containment for an improved Mark-II Boiling Water Reactor plant in Japan. The contact structure, which is ... continued below

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14 p.

Creation Information

Costello, J. F.; Ludwigsen, J. S.; Luk, V. K. & Hessheimer, M. F. January 6, 2000.

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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. 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 Nuclear Power Engineering Corporation of Japan and the US Nuclear Regulatory Commission Office of Nuclear Regulatory Research, are co-sponsoring and jointly funding a Cooperative Containment Research Program at Sandia National Laboratories, Albuquerque, New Mexico, USA. As a part of this program, a steel containment vessel model and contact structure assembly was tested to failure with over pressurization at Sandia on December 11--12, 1996. The steel containment vessel model was a mixed-scale model (1:10 in geometry and 1:4 in shell thickness) of a steel containment for an improved Mark-II Boiling Water Reactor plant in Japan. The contact structure, which is a thick, bell-shaped steel shell separated at a nominally uniform distance from the model, provides a simplified representation of features of the concrete reactor shield building in the actual plant. The objective of the internal pressurization test was to provide measurement data of the structural response of the model up to its failure in order to validate analytical modeling, to find its pressure capacity, and to observe the failure model and mechanisms.

Physical Description

14 p.

Notes

INIS; OSTI as DE00750233

Medium: P; Size: 14 pages

Source

  • ICONE, Baltimore, MD (US), 04/02/2000--04/06/2000

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  • Report No.: SAND2000-0051C
  • Grant Number: AC04-94AL85000
  • Office of Scientific & Technical Information Report Number: 750233
  • Archival Resource Key: ark:/67531/metadc706693

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Creation Date

  • January 6, 2000

Added to The UNT Digital Library

  • Sept. 12, 2015, 6:31 a.m.

Description Last Updated

  • April 7, 2017, 2:37 p.m.

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Costello, J. F.; Ludwigsen, J. S.; Luk, V. K. & Hessheimer, M. F. Predictability of steel containment response near failure, article, January 6, 2000; Albuquerque, New Mexico. (digital.library.unt.edu/ark:/67531/metadc706693/: accessed September 22, 2017), University of North Texas Libraries, Digital Library, digital.library.unt.edu; crediting UNT Libraries Government Documents Department.