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Title: Effect of in-PWR irradiation on size, structure, and composition of intermetallic precipitates of Zr alloys

Abstract

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{sup {minus}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){sub 2}, Zr{sub 2}(Fe,Si), and Zr{sub 3}Fe 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 Zr{sub 3}Fe 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 transitionmore » from irradiation-induced dissolution to irradiation-induced growth by a normalized (homologous) temperature led to reasonable results.« less

Authors:
; ;  [1];  [2]
  1. Siemens AG, Erlangen (Germany). Power Generation Group
  2. Inst. for Transuranium Elements, Karlsruhe (Germany)
Publication Date:
OSTI Identifier:
479452
Report Number(s):
CONF-950926-
Journal ID: ISSN 1050-7558; TRN: 97:010521
Resource Type:
Conference
Resource Relation:
Conference: 11. international symposium on zirconium in the nuclear industry, Garmisch-Partenkirchen (Germany), 11-14 Sep 1995; Other Information: PBD: 1996; Related Information: Is Part Of Zirconium in the nuclear industry: Eleventh international symposium; Bradley, E.R. [ed.] [Sandvik Special Metals Corp., Kennewick, WA (United States)]; Sabol, G.P. [ed.] [Westinghouse Electric Corp., Pittsburgh, PA (United States)]; PB: 911 p.; American Society for Testing and Materials STP 1295
Country of Publication:
United States
Language:
English
Subject:
36 MATERIALS SCIENCE; 21 NUCLEAR POWER REACTORS AND ASSOCIATED PLANTS; ZIRCONIUM BASE ALLOYS; PHYSICAL RADIATION EFFECTS; PWR TYPE REACTORS; CORROSION; MICROSTRUCTURE; TEMPERATURE DEPENDENCE; INTERMETALLIC COMPOUNDS; PRECIPITATION

Citation Formats

Garzarolli, F, Goll, W, Seibold, A, and Ray, I. Effect of in-PWR irradiation on size, structure, and composition of intermetallic precipitates of Zr alloys. United States: N. p., 1996. Web.
Garzarolli, F, Goll, W, Seibold, A, & Ray, I. Effect of in-PWR irradiation on size, structure, and composition of intermetallic precipitates of Zr alloys. United States.
Garzarolli, F, Goll, W, Seibold, A, and Ray, I. 1996. "Effect of in-PWR irradiation on size, structure, and composition of intermetallic precipitates of Zr alloys". United States.
@article{osti_479452,
title = {Effect of in-PWR irradiation on size, structure, and composition of intermetallic precipitates of Zr alloys},
author = {Garzarolli, F and Goll, W and Seibold, A and Ray, I},
abstractNote = {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{sup {minus}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){sub 2}, Zr{sub 2}(Fe,Si), and Zr{sub 3}Fe 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 Zr{sub 3}Fe 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.},
doi = {},
url = {https://www.osti.gov/biblio/479452}, journal = {},
issn = {1050-7558},
number = ,
volume = ,
place = {United States},
year = {1996},
month = {12}
}

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