Effect of in-PWR irradiation on size, structure, and composition of intermetallic precipitates of Zr alloys
Creators
- 1. Siemens AG, Erlangen (Germany). Power Generation Group
- 2. Inst. for Transuranium Elements, Karlsruhe (Germany)
Description
The corrosion behavior of Zr alloys depends on the kind, size, and distribution of the intermetallic second-phase particles. TEM examinations of Zr-Sn-Fe-Cr alloys irradiated in PWRs at temperatures between 300 and 370 C and fast fluences in the range of 5E21 to 1.3E22 cm-2 have been performed to study the irradiation-induced effects on the precipitates. The alloys contained different types of second-phase particles such as Zr(Fe,Cr)2, Zr2(Fe,Si), and Zr3Fe before irradiation. The influence of irradiation was found to depend on temperature and type of second-phase particles. In Fe-containing Sr alloys with little or no Cr, rather large Zr3Fe precipitates are the most frequent particles. These particles are not dissolved by irradiation even at low temperatures. This was confirmed by annealing after irradiation. As a hypothesis, it was assumed that the different behavior of the various precipitates can be related to their melting or decomposition temperatures by using the homologous temperature (i.e., the temperature under consideration in K normalized to the melting or decomposition temperature in K). This interrelationship has been found to apply for irradiation-induced amorphization. The empirical approach to describe the thermal ripening behavior of second-phase particles before irradiation and to describe the transition from irradiation-induced dissolution to irradiation-induced growth by a normalized (homologous) temperature led to reasonable results
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. 541-556.
- 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
- 28058512
- Subject category
- S36: MATERIALS SCIENCE; S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- CORROSION; INTERMETALLIC COMPOUNDS; MICROSTRUCTURE; PHYSICAL RADIATION EFFECTS; PRECIPITATION; PWR TYPE REACTORS; TEMPERATURE DEPENDENCE; ZIRCONIUM BASE ALLOYS
- Descriptors DEC
- ALLOYS; CHEMICAL REACTIONS; CRYSTAL STRUCTURE; ENRICHED URANIUM REACTORS; POWER REACTORS; RADIATION EFFECTS; REACTORS; SEPARATION PROCESSES; THERMAL REACTORS; TRANSITION ELEMENT ALLOYS; WATER COOLED REACTORS; WATER MODERATED REACTORS; ZIRCONIUM ALLOYS
Optional Information
- Secondary number(s)
- CONF-950926--.