Stresses in reactor pressure vessel nozzles -- Calculations and experiments
- Nuclear Research Institute Rez plc (Czech Republic)
- 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; TRN: 95:024199
- Resource Relation:
- Conference: Joint American Society of Mechanical Engineers (ASME)/Japan Society of Mechanical Engineers (JSME) pressure vessels and piping conference, Honolulu, HI (United States), 23-27 Jul 1995; Other Information: PBD: 1995; Related Information: Is Part Of Composites for the pressure vessel industry. PVP-Volume 302; Bees, W.J.; Newaz, G.M.; Narita, Yoshihiro; Takezono, S.; Qatu, M.S.; Hirano, T.; Miyazaki, N.; Nakagaki, M. [eds.]; PB: 312 p.
- Country of Publication:
- United States
- Language:
- English
Similar Records
Strength and fracture behavior of a cracked feedwater-nozzle corner in a BWR pressure vessel under operational loading
Development of Digital Twin Predictive Model for PWR Components: Updates on Multi Times Series Temperature Prediction Using Recurrent Neural Network, DMW Fatigue Tests, System Level Thermal-Mechanical-Stress Analysis