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U.S. Department of Energy
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Stresses in reactor pressure vessel nozzles -- Calculations and experiments

Book ·
OSTI ID:122540
 [1];  [2]
  1. Nuclear Research Institute Rez plc (Czech Republic)
  2. Nuclear Machinery, Ltd. Plzen (Czech Republic)
Reactor pressure vessel nozzles are characterized by a high stress concentration which is critical in their low-cycle fatigue assessment. Program of experimental verification of stress/strain field distribution during elastic-plastic loading of a reactor pressure vessel WWER-1000 primary nozzle model in scale 1:3 is presented. While primary nozzle has an ID equal to 850 mm, the model nozzle has ID equal to 280 mm, and was made from 15Kh2NMFA type of steel. Calculation using analytical methods was performed. Comparison of results using different analytical methods -- Neuber`s, Hardrath-Ohman`s as well as equivalent energy ones, used in different reactor Codes -- is shown. Experimental verification was carried out on model nozzles loaded statically as well as by repeated loading, both in elastic-plastic region. Strain fields were measured using high-strain gauges, which were located in different distances from center of nozzle radius, thus different stress concentration values were reached. Comparison of calculated and experimental data are shown and compared.
OSTI ID:
122540
Report Number(s):
CONF-950740--; ISBN 0-7918-1333-9
Country of Publication:
United States
Language:
English