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Atomic Energy

, Volume 92, Issue 5, pp 367–372 | Cite as

Some Problems of Large-Scale Safety Test Stands

  • V. N. Smolin
  • V. P. Shishov
  • V. I. Grachev
  • A. I. Ionov
  • A. I. Emel'yanov
  • T. K. Sedova
  • S. M. Balashov
Article
  • 23 Downloads

Abstract

Certain problems associated with the design and construction of and the results of work performed on large-scale safety test stands for water-moderated water-cooled, channel, and boiling-water vessel reactors are presented. It is shown that inadequate adherence to simulation principles in experimental setups can result in incorrect results concerning the effectiveness of emergency core-cooling systems in reactors.

The results obtained in this country and abroad show that a successful design, technological effectiveness, and reliability of all components of the model of a reactor core prevent the loss of time and resources in performing experimental programs. For example, such losses resulting from frequent failures of fuel element simulators, which are technologically highly effective and critical components of test stands, can be eliminated.

Keywords

Critical Component Vessel Reactor Element Simulator Fuel Element Experimental Program 
These keywords were added by machine and not by the authors. This process is experimental and the keywords may be updated as the learning algorithm improves.

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Copyright information

© Plenum Publishing Corporation 2002

Authors and Affiliations

  • V. N. Smolin
    • 1
  • V. P. Shishov
    • 1
  • V. I. Grachev
    • 1
  • A. I. Ionov
    • 1
  • A. I. Emel'yanov
    • 1
  • T. K. Sedova
    • 1
  • S. M. Balashov
    • 1
  1. 1.Federal State Unitary EnterpriseN. A. Dollezhal' Scientific-Research and Design Institute for Power EngineeringRussia

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