Evolution of dislocation microstructure in irradiated Zr alloys determined by X-ray peak profile analysis.

Ildikó Szenthe,Gyula Zilahi,Éva Ódor,Bertalan Jóni,Gábor Ribárik,Zoltán Hózer,István Groma,Zoltán Dankházi

doi:10.1107/s1600576720015885

Abstract

During neutron irradiation of metals, owing to the enhanced number of vacancies and interstitial atoms, the climb motion of dislocations becomes significant at room temperature, leading to a recrystallization of the material. Moreover, the vacancies and interstitial atoms tend to form prismatic dislocation loops that play a crucial role in the plastic properties of the materials. X-ray peak profile analysis is an efficient nondestructive method to determine the properties of dislocation microstructure. In the first half of this article, the foundation of the asymptotic peak broadening theory and the related restricted-moments peak-evaluation method is summarized. After this, the microstructural parameters obtained by X-ray peak profile analysis are reported for irradiated E110 and E110G Zr alloys used as cladding material in the nuclear industry.

Highlights

One of the constant objectives of various technical and economic improvements related to nuclear reactors is the sustainable and increasingly safe operation of existing reactors
During the operation of nuclear reactors, radioactive fission products are produced in the fuel elements
Since during the manufacturing of the cladding tube the grains in the materials undergo a complex deformation it is assumed that the possible dislocation types in the different slip systems are activated with equal probability

Summary

Introduction

One of the constant objectives of various technical and economic improvements related to nuclear reactors is the sustainable and increasingly safe operation of existing reactors. Increasing safety requirements are a constant challenge in optimizing the properties of reactor materials. During the operation of nuclear reactors, radioactive fission products are produced in the fuel elements. These fission products can produce radiation dangerous to living organisms. The most important task of the fuel-element cladding is to act as a primary barrier to the release of radioactive isotopes from the fuel rods into the primary coolant and potentially to the environment. Even under extreme operating conditions, it is necessary to preserve the integrity of the cladding tubes

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Discussion

Conclusion