Deformation and failure of Zircaloy fuel sheaths under LOCA conditions
Creators
- 1. Atomic Energy of Canada Ltd., Chalk River Labs., Ontario
Description
A unified, microstructural creep law which simulates the transient creep deformation of Zircaloy at temperatures above 750 K has been used to follow the interaction of diffusional and dislocation creep with changes in material microstructure (grain size, recrystallization, phase fraction and anisotropy) under loss-of-coolant accident (LOCA) conditions. Comparison of a membrane sheath model using this creep law with a large number of tube tests (>700) in an inert environment has demonstrated good predictive capability. This model has been extended to cover other aspects affecting deformation and failure of CANDU (CANada Deuterium Uranium) fuel sheaths such as: nonuniform structure distribution resulting from temperature profiles along the sheath length, oxidation of the fuel sheaths, cracking of the oxidized layers and localized straining, large strain failure, and failure by beryllium-assisted cracking
Additional details
Publishing Information
- Publisher
- American Society for Testing and Materials.
- Imprint Place
- Philadelphia, PA (USA)
- Imprint Title
- Zirconium in the nuclear industry
- Journal Page Range
- p. 709-733.
Conference
- Title
- 6. international conference on zirconium in the nuclear industry.
- Dates
- 28 Jun - 1 Jul 1982.
- Place
- Vancouver, British Columbia (Canada).
INIS
- Country of Publication
- United States
- Country of Input or Organization
- United States
- INIS RN
- 16064876
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS; S36: MATERIALS SCIENCE;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- ANISOTROPY; BERYLLIUM; CANDU TYPE REACTORS; CRACK PROPAGATION; CREEP; DEFORMATION; DIFFUSION; DISLOCATIONS; FAILURES; FUEL CANS; FUEL ELEMENTS; GRAIN SIZE; HIGH TEMPERATURE; LOSS OF COOLANT; MICROSTRUCTURE; OXIDATION; PHYSICAL RADIATION EFFECTS; REACTOR MATERIALS; RECRYSTALLIZATION; STRAINS; THERMAL STRESSES; ZIRCALOY
- Descriptors DEC
- ACCIDENTS; ALKALINE EARTH METALS; ALLOYS; CHEMICAL REACTIONS; CRYSTAL DEFECTS; CRYSTAL STRUCTURE; ELEMENTS; HEAVY WATER MODERATED REACTORS; LINE DEFECTS; MATERIALS; MECHANICAL PROPERTIES; METALS; POWER REACTORS; PRESSURE TUBE REACTORS; RADIATION EFFECTS; REACTOR ACCIDENTS; REACTOR COMPONENTS; REACTORS; SIZE; STRESSES; THERMAL REACTORS; ZIRCONIUM ALLOYS; ZIRCONIUM BASE ALLOYS