Abstract

Neutron irradiation progressively changes the properties of zirconium alloys: they harden and their average c/a lattice parameter ratio decreases with fluence [1, 2, 3, 4]. The bombardment by neutrons produces point defects, which evolve into dislocation loops that contribute to a non-uniform growth phenomenon called irradiation-induced growth (IIG). To gain insights into these dislocation loops in Zr we studied them using atomistic simulation. We constructed and relaxed dislocation loops of various types. We find that the energies of 〈a〉 loops on different habit planes are similar, but our results indicate that they are most likely to form on the 1st prismatic plane and then reduce their energy by rotating onto the 2nd prismatic plane. By simulating loops of different aspect ratios, we find that, based on energetics alone, the shape of 〈a〉 loops does not depend on character, and that these loops become increasingly elliptical as their size increases. Additionally, we find that interstitial 〈c/2+p〉 loops and vacancy 〈c〉 loops are both energetically feasible and so the possibility of these should be considered in future work. Our findings offer important insights into loop formation and evolution, which are difficult to probe experimentally.

Highlights

  • Zirconium alloys are used in light water nuclear power reactors in several applications, in particular for nuclear fuel cladding

  • Christiaen et al modelled stacking fault bipyramids on the basal plane, with molecular statics (MS), using the M&A #3 potential, and with density functional theory (DFT) [55]. They removed two layers of hexagonal close-packed (HCP) crystal, with the aim of creating a perfect c loop and relaxed this with DFT and MS. This produced a bipyramid on the basal plane and this gradually changed into a c loop as more vacancies were removed from the starting configuration

  • In their DFT results they saw a shift from the BB stacking pattern, to an I1 stacking fault, characteristic of a c/2+p loop, but the MS simulations retained their BB stacking pattern

Read more

Summary

Introduction

Zirconium alloys are used in light water nuclear power reactors in several applications, in particular for nuclear fuel cladding. These reactors operate at temperatures from around 350 K to about 580 K [5]. Recrystallised Zr alloy guide tubes and grids suffer from irradiationinduced growth (IIG), which occurs in three phases: initial, steady and breakaway [7]. The growth curve gradient flattens and there is a long phase where little or no growth occurs. IIG is an anisotropic growth and varies from tube to tube This can cause the fuel rods to buckle, leading to problems such as hot spots [9]. Note that IIG is one phenomenon that may contribute to fuel rod deformation, but other phenomena, such as pellet cladding interaction, may contribute [10]

Methods
Results
Conclusion
Full Text
Published version (Free)

Talk to us

Join us for a 30 min session where you can share your feedback and ask us any queries you have

Schedule a call