Engineering Mechanics

Proceedings Vol. 10 (2004)

ENGINEERING MECHANICS 2004

Copyright © 2004 Institute of Thermomechanics, Academy of Sciences of the Czech Republic, Prague

 

Macák P., Pechmannová E.
pages 171 - +10p., full text

The subject matter of this paper is a brief description of the methodology as well as a presentation of conclusions following from the service life exhaustion assessment of pressure vessel of the reactor WWER 1000 (RPV) made after test operation gone at the NPP Temelín Unit 1. The methodology of the assessment comes from low-cycle fatigue analysis and evaluation of the fatigue damage at selected points in the RPV. The time history of operation parameters taken from the sources available at the NPP became a set of input data to the analysis. The Russian Standard PNAE G-7-002-86 is a basis for setting up the algorithm to evaluate a value of the summary fatigue damage.

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