Plastic energy dissipation model for lifetime prediction of zirconium and zircaloy-4 fatigued at RT and 400 C
Creators
- 1. Xi'an Jiaotong Univ. (China). State Key Lab. for Mechanical Behavior of Materials
Description
Zirconium and zircaloy-4 are generally used as fuel tubes in pressurized heavy water reactors because of their low neutron absorption cross-section, excellent corrosion resistance, good strength and ductility. Low cycle fatigue properties of zirconium and zircaloy-4 were investigated at RT and 400 C. The microscopic structure was determined using scanning electron microscopy and transmission electron microscopy techniques. On the basis of analyses of fatigue damage mechanism, it is believed that fatigue is an irreversible energy dissipation process. Thus, the plastic dissipation energy per cycle is selected as a fatigue damage variable. The accumulated plastic dissipation energy is calculated at the condition of considering cyclic hardening, saturation and softening characters of zirconium and zircaloy-4 during cycling. The testing results show that they present a power law between the plastic dissipation energy and fatigue lifetime
Additional details
Publishing Information
- Journal Title
- Journal of Engineering Materials and Technology
- Journal Volume
- 120
- Journal Issue
- 2
- Journal Page Range
- p. 114-118
- ISSN
- 0094-4289
- CODEN
- JEMTA8
INIS
- Country of Publication
- United States
- Country of Input or Organization
- United States
- INIS RN
- 29052648
- Subject category
- S36: MATERIALS SCIENCE; S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Descriptors DEI
- ENERGY LOSSES; FATIGUE; MATHEMATICAL MODELS; MICROSTRUCTURE; PWR TYPE REACTORS; SERVICE LIFE; TEMPERATURE RANGE 0273-0400 K; ZIRCALOY 4; ZIRCONIUM
- Descriptors DEC
- ALLOY-ZR98SN-4; ALLOYS; CHROMIUM ADDITIONS; CORROSION RESISTANT ALLOYS; CRYSTAL STRUCTURE; ELEMENTS; ENRICHED URANIUM REACTORS; HEAT RESISTANT MATERIALS; HEAT RESISTING ALLOYS; IRON ADDITIONS; LIFETIME; MATERIALS; MECHANICAL PROPERTIES; METALS; POWER REACTORS; REACTORS; TEMPERATURE RANGE; THERMAL REACTORS; TIN ALLOYS; TRANSITION ELEMENT ALLOYS; TRANSITION ELEMENTS; WATER COOLED REACTORS; WATER MODERATED REACTORS; ZIRCALOY; ZIRCONIUM ALLOYS; ZIRCONIUM BASE ALLOYS