The paper presents the physical and mechanical model that allows predicting fracture of materials subjected to neutron irradiation under creep. The model is based on the equations of void nucleation and growth on grain boundaries that were proposed earlier. The equations are developed for the case of neutron irradiation of a material. The constitutive equations describing viscoplastic deformation of a material with regard to void evolution are formulated. The criterion of microplastic collapse of a unit cell is used as a fracture criterion. The creep-rupture strength and ductility of austenitic materials in the initial and irradiated conditions with different neutron flux levels are predicted on the basis of the model. The calculated results are compared with the available experimental data.
Skip Nav Destination
ASME 2009 Pressure Vessels and Piping Conference
July 26–30, 2009
Prague, Czech Republic
Conference Sponsors:
- Pressure Vessels and Piping
ISBN:
978-0-7918-4369-7
PROCEEDINGS PAPER
Prediction of Creep-Rupture Properties for Austenitic Steels Undergone Neutron Irradiation
B. Z. Margolin,
B. Z. Margolin
Central Research Institute of Structural Materials “Prometey”, Saint-Petersburg, Russia
Search for other works by this author on:
A. G. Gulenko,
A. G. Gulenko
Central Research Institute of Structural Materials “Prometey”, Saint-Petersburg, Russia
Search for other works by this author on:
A. A. Buchatsky
A. A. Buchatsky
Central Research Institute of Structural Materials “Prometey”, Saint-Petersburg, Russia
Search for other works by this author on:
B. Z. Margolin
Central Research Institute of Structural Materials “Prometey”, Saint-Petersburg, Russia
A. G. Gulenko
Central Research Institute of Structural Materials “Prometey”, Saint-Petersburg, Russia
A. A. Buchatsky
Central Research Institute of Structural Materials “Prometey”, Saint-Petersburg, Russia
Paper No:
PVP2009-77084, pp. 949-958; 10 pages
Published Online:
July 9, 2010
Citation
Margolin, BZ, Gulenko, AG, & Buchatsky, AA. "Prediction of Creep-Rupture Properties for Austenitic Steels Undergone Neutron Irradiation." Proceedings of the ASME 2009 Pressure Vessels and Piping Conference. Volume 6: Materials and Fabrication, Parts A and B. Prague, Czech Republic. July 26–30, 2009. pp. 949-958. ASME. https://doi.org/10.1115/PVP2009-77084
Download citation file:
7
Views
Related Proceedings Papers
Related Articles
Irradiation Effects on the Behavior of Structural Materials at Elevated Temperature
J. Eng. Mater. Technol (April,1978)
Sulfur Effects on High-Temperature Creep and Fracture Behavior of 25Cr35Ni–Nb Alloys
J. Pressure Vessel Technol (August,2014)
Creep Damage in a Cr-Mo-V Steel as Measured by Retained Stress Rupture Properties
Trans. ASME (January,1957)
Related Chapters
Introduction and Definitions
Handbook on Stiffness & Damping in Mechanical Design
A Mechanism of Intergranular Fracture During High-Temperature Fatigue
Fatigue Mechanisms
Subsection NB—Class 1 Components
Companion Guide to the ASME Boiler and Pressure Vessel Code, Volume 1, Fourth Edition