The influence of temperature and yield strength on delayed hydride cracking in hydrided Zircaloy-2
Description
To determine if delayed hydride cracking (DHC) can be the cause of the long axial cracks occasionally found in BWR fuel cladding, a systematic study of DHC in Zircaloy cladding has begun. In the initial stage of the project, a test technique was developed and applied to unirradiated samples of Zircaloy. The present study includes an investigation of the influence of the yield strength and temperature on the crack growth rate and the threshold stress intensity that must be exceeded before cracking begins. Recrystallized (RXA) Zircaloy-2 has been compared to stress relief annealed (SRA) Zircaloy-2 with similar texture and composition. The results show that the crack propagation rate increases with increasing yield strength at similar stress intensity levels by as much as a decade when the yield strength is tripled. The maximum crack propagation rate measured in this study is ∼6 x 10-7 m/s. The threshold stress intensity, KIH, was found to decrease with increasing yield stress. The measured threshold values are in the range of 13.5 to 7.5 MPa. These figures are close to theoretically derived values using a critical fracture stress criterion of the hydrides as the limiting factor. The incubation period before cracking begins is found to be longer at 200 C than it is at 300 C
Additional details
Publishing Information
- Publisher
- American Society for Testing and Materials.
- Imprint Place
- West Conshohocken, PA (United States)
- ISBN
- 0-8031-2406-6
- Imprint Title
- Zirconium in the nuclear industry: Eleventh international symposium
- Imprint Pagination
- 911 p.
- Series
- American Society for Testing and Materials STP 1295.
- Journal Page Range
- p. 394-404.
- ISSN
- 1050-7558
Conference
- Title
- 11. international symposium on zirconium in the nuclear industry.
- Dates
- 11-14 Sep 1995.
- Place
- Garmisch-Partenkirchen (Germany).
INIS
- Country of Publication
- United States
- Country of Input or Organization
- United States
- INIS RN
- 28058446
- Subject category
- S36: MATERIALS SCIENCE; S36: MATERIALS SCIENCE; S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- BWR TYPE REACTORS; CRACK PROPAGATION; FUEL CANS; HYDRIDATION; HYDROGEN EMBRITTLEMENT; STRESS INTENSITY FACTORS; TEMPERATURE DEPENDENCE; ZIRCALOY 2
- Descriptors DEC
- ALLOY-ZR98SN-2; ALLOYS; CHEMICAL REACTIONS; CHROMIUM ADDITIONS; CORROSION RESISTANT ALLOYS; EMBRITTLEMENT; ENRICHED URANIUM REACTORS; HEAT RESISTANT MATERIALS; HEAT RESISTING ALLOYS; IRON ADDITIONS; MATERIALS; NICKEL ADDITIONS; POWER REACTORS; REACTORS; THERMAL REACTORS; TIN ALLOYS; TRANSITION ELEMENT ALLOYS; WATER COOLED REACTORS; WATER MODERATED REACTORS; ZIRCALOY; ZIRCONIUM ALLOYS; ZIRCONIUM BASE ALLOYS
Optional Information
- Secondary number(s)
- CONF-950926--.