Published 1997 | Version v1
Report Restricted

Testing of a steel containment vessel model

  • 1. Sandia National Labs., Albuquerque, NM (United States)
  • 2. Nuclear Power Engineering Corp., Tokyo (Japan)
  • 3. Nuclear Regulatory Commission, Washington, DC (United States)

Description

A mixed-scale containment vessel model, with 1:10 in containment geometry and 1:4 in shell thickness, was fabricated to represent an improved, boiling water reactor (BWR) Mark II containment vessel. A contact structure, installed over the model and separated at a nominally uniform distance from it, provided a simplified representation of a reactor shield building in the actual plant. This paper describes the pretest preparations and the conduct of the high pressure test of the model performed on December 11-12, 1996. 4 refs., 2 figs

Availability note (English)

Available from INIS in electronic form and/or on microfiche ; Also available from OSTI as DE97004646; NTIS; US Govt. Printing Office Dep.

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Additional details

Publishing Information

Imprint Pagination
7 p.
Report number
SAND--97-0837C

Conference

Title
14. international conference on structural mechanics in reactor technology (SMIRT).
Dates
17-22 Aug 1997.
Place
Lyon (France).

Optional Information