Effect of proton and Ne irradiation on the microstructure of Zircaloy 4

Proton irradiation at temperatures of 310 and 350°C has been explored as a method of studying radiation effects in Zircaloy 4 under power-reactor conditions. The dislocation-loop and hardness evolution are similar to those observed under neutron irradiation. Amorphization and Fe loss at Zr(Cr,Fe)2 precipitates are observed. Energy-filtered images indicate Fe accumulation in the matrix near the precipitate, a phenomenon not reported in neutron-irradiated alloys.

[1]  Stephen M. Bruemmer,et al.  Emulation of neutron irradiation effects with protons: validation of principle , 2002 .

[2]  D. Gosset,et al.  Analysis of the monoclinic–tetragonal phase transition of zirconia under irradiation , 2002 .

[3]  E. Kenik,et al.  Microchemistry and microstructure of proton-irradiated austenitic alloys: toward an understanding of irradiation effects in LWR core components , 1999 .

[4]  A. Motta.  Amorphization of intermetallic compounds under irradiation - A review , 1997 .

[5]  V. Markelov,et al.  Irradiation-induced microstructural changes in Zr-1% Sn-1% Nb-0.4% Fe , 1996 .

[6]  A. Motta,et al.  The formation of bubbles in Zr alloys under Kr ion irradiation , 1996 .

[7]  S. Zinkle,et al.  Microstructure of irradiated materials , 1995 .

[8]  G. E. Lucas,et al.  The evolution of mechanical property change in irradiated austenitic stainless steels , 1993 .

[9]  Y. Etoh,et al.  Neutron irradiation effects on intermetallic precipitates in Zircaloy as a function of fluence , 1993 .

[10]  A. Motta,et al.  Precipitate evolution in the Zircaloy-4 oxide layer , 1992 .

[11]  G. Was,et al.  Proton-induced grain boundary segregation in stainless steel , 1991 .

[12]  M. Griffiths.  Comments on precipitate stability in neutron-irradiated Zircaloy-4 , 1990 .

[13]  J. Kai,et al.  The microstructural evolution of zircaloy-4 subjected to proton irradiation , 1990 .

[14]  W. Yang.  Precipitate stability in neutron-irradiated Zircaloy-4 , 1988 .

[15]  M. Nagai,et al.  Reduction of plastic anisotropy of Zircaloy cladding by neutron irradiation. I. Yield loci obtained from Knoop hardness , 1987 .

[16]  S. Shimada,et al.  Evaluation of the resistance of irradiated zirconium-liner cladding to iodine-induced stress corrosion cracking , 1983 .

[17]  H. R. Higgy,et al.  EFFECT OF NEUTRON IRRADIATION ON THE TENSILE PROPERTIES OF ZIRCALOY-2 AND ZIRCALOY-4. , 1972 .