Use and Development of Coupled Computer Codes for the Analysis of Accidents at Nuclear Power Plants

Summarizes the results of the Technical Meeting on Progress in Development and Use of Coupled Codes for Accident Analysis. This publication contains a review of state of the art technologies in code coupling and its application to the accident analysis of nuclear power plants.

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This publication summarizes the results of the Technical Meeting on Progress in Development and Use of Coupled Codes for Accident Analysis. The significantly increased capacity of new computation technology has made it possible to develop the use of code coupling not only between neutronics and thermal hydraulics, but also between thermal hydraulics and one or more other disciplines. This publication contains a review of state of the art technologies in code coupling and its application to the accident analysis of nuclear power plants. The presentations and the papers given at the meeting are included on the attached CD-ROM.