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Emulation of neutron damage with proton irradiation and its effects on microstructure and microchemistry of Zircaloy-4

Journal Article · · Journal of Nuclear Materials
 [1];  [2];  [3];  [4];  [4];  [4];  [2];  [2];  [1]
  1. University of Michigan, Ann Arbor, MI (United States)
  2. Pennsylvania State University, University Park, PA (United States)
  3. Idaho National Laboratory (INL), Idaho Falls, ID (United States)
  4. Bettis Atomic Power Laboratory (BAPL), Pittsburgh, PA (United States)
This work assesses the potential of proton irradiation to simulate the neutron damage to the matrix and laves phase Zr(Fe,Cr)2 precipitates in Zircaloy-4. Isothermal proton irradiation has been performed on Zircaloy-4 samples at irradiation temperatures ranging from 250 to 350 °C. Two-step proton irradiation was also performed to enhance the amorphization of and iron loss from the laves phase Zr(Fe,Cr)2 precipitates. The irradiated microstructures, including dislocation loops and rafts near SPPs, were observed in proton irradiated Zircaloy-4, which are consistent with neutron irradiated material at a similar damage level. The amount of irradiation-induced hardening after proton irradiation was similar to post neutron irradiated data. The significant amorphization of the SPPs and concurrent Fe redistribution observed on neutron irradiated materials can be effectively emulated using a two-step proton irradiation on Zircaloy-4. Hence, the neutron irradiation effect on Zircaloy-4 can be mostly captured using the two-step proton irradiation described in this study.
Research Organization:
Idaho National Laboratory (INL), Idaho Falls, ID (United States)
Sponsoring Organization:
USDOE Laboratory Directed Research and Development (LDRD) Program; USDOE Office of Nuclear Energy (NE)
Grant/Contract Number:
89233018CNR000004; AC07-05ID14517
OSTI ID:
1959043
Alternate ID(s):
OSTI ID: 1974883
Report Number(s):
INL/JOU-20-59449-Revision-1; INL/JOU-22-52234-Revision-1
Journal Information:
Journal of Nuclear Materials, Journal Name: Journal of Nuclear Materials Vol. 557; ISSN 0022-3115
Publisher:
ElsevierCopyright Statement
Country of Publication:
United States
Language:
English

References (35)

Characterization of neutron irradiation damage in zirconium alloys — an international “round-robin” experiment journal February 1979
Evaluation of the resistance of irradiated zirconium-liner cladding to iodine-induced stress corrosion cracking journal February 1983
〈〉 Component dislocations in annealed Zircaloy irradiated at about 570 K journal February 1986
The formation of c-component defects in zirconium alloys during neutron irradiation journal October 1987
Phase instability, decomposition and redistribution of intermetallic precipitates in Zircaloy-2 and -4 during neutron irradiation journal September 1987
A review of microstructure evolution in zirconium alloys during irradiation journal October 1988
Comments on precipitate stability in neutron-irradiated Zircaloy-4 journal March 1990
Effects of microchemistry and precipitate size on nodular corrosion resistance of Zircaloy-2 journal July 1992
Neutron irradiation effects on intermetallic precipitates in Zircaloy as a function of fluence journal March 1993
Dissolution of zirconium oxide films in 300°C LiOH journal February 1993
The effect of matrix chemistry on dislocation evolution in an irradiated Zr alloy journal May 2017
Mechanism of corrosion of zirconium hydride and impact of precipitated hydrides on the Zircaloy-4 corrosion behaviour journal September 2015
Some thoughts on the mechanisms of in-reactor corrosion of zirconium alloys journal February 2005
Proton irradiation effect on microstructure, strain localization and iodine-induced stress corrosion cracking in Zircaloy-4 journal January 2009
Experimental study of the nucleation and growth of c-component loops under charged particle irradiations of recrystallized Zircaloy-4 journal June 2012
Irradiation induced microstructural changes in Zr-Excel alloy journal October 2013
Analysis of atomic distribution in as-fabricated Zircaloy-2 claddings by atom probe tomography under high-energy pulsed laser journal November 2013
Development of microstructure and irradiation hardening of Zircaloy during low dose neutron irradiation at nominally 377–440°C journal June 2014
Redistribution of alloying elements in Zircaloy-2 after in-reactor exposure journal November 2014
Iron redistribution in a zirconium alloy after neutron and proton irradiation studied by energy-dispersive X-ray spectroscopy (EDX) using an aberration-corrected (scanning) transmission electron microscope journal November 2014
Nano-scale chemical evolution in a proton-and neutron-irradiated Zr alloy journal April 2017
The role of hydrogen in zirconium alloy corrosion journal December 2017
The characterisation of second phases in the Zr-Nb and Zr-Nb-Sn-Fe alloys: A critical review journal July 2018
The effect of irradiation temperature on damage structures in proton-irradiated zirconium alloys journal February 2019
A solution to FIB induced artefact hydrides in Zr alloys journal March 2019
Determination of dose rate effects on Zircaloy oxidation using proton irradiation and oxygen transport modeling journal September 2019
The formation and stacking faults of Fe and Cr containing Laves phase in Zircaloy-4 alloy journal March 2017
Effects of ion irradiation on microstructure and properties of zirconium alloys—A review journal April 2015
On the use of SRIM for computing radiation damage exposure journal September 2013
Atom probe examinations of Zircaloy irradiated at nominally 358 °C journal May 2019
Microstructural and Microchemical Analyses of Extracted Second-Phase Precipitates in Alpha-Annealed and Beta-Quenched Zircaloy-4 journal August 2014
Effect of proton and Ne irradiation on the microstructure of Zircaloy 4 journal February 2005
Reduction of Plastic Anisotropy of Zircaloy Cladding by Neutron Irradiation, (I): Yield Loci Obtained from Knoop Hardness journal October 1987
The quantitative analysis of thin specimens journal March 1975
Radiation Damage in Zirconium and its Alloys journal January 1987

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