Abstract

In metallurgical applications, precipitation strengthening is of great technological importance to engineer materials with the required strength. While precipitation hardening is essential for many applications involving operation at elevated temperatures, its subsequent embrittlement can be a showstopper for the overall performance of a component. In the nuclear industry, irradiation-induced/enhanced precipitation and the resulting embrittlement often limit the lifetime of components. In fusion applications, tungsten (W) based alloys are known to harden and embrittle as a result of irradiation-assisted transmutation to rhenium (Re) and its subsequent precipitation into non-coherent precipitates. Hence, a fundamental understanding of the interaction of dislocations with non-coherent precipitates is of great interest. In the present work, the interaction of dislocations with non-coherent Re-rich σ, χ and hcp phase precipitates embedded in a bcc W matrix is assessed. Large-scale atomistic simulations are performed to clarify the interaction mechanisms and derive the obstacle strength of the precipitates in the quasi-static limit. Thereby the impact of precipitate shape, size, interspacing and composition is assessed. Based on those results, an analytical model to predict precipitation hardening of σ, χ and hcp phase particles in bcc W is proposed and compared to available experimental data from mechanical tests on irradiated materials.

Highlights

  • In metallurgical applications, precipitation strengthening is of great technological importance to engineer materials with the required strength

  • Precipitation hardening is essential to improve the alloys’ strength, e.g., precipitation strengthening of Al-based alloys used in the aerospace industry, carbo-nitride precipitation to improve the high temperature strength of ferritic-martensitic steels, etc

  • Tungsten is the material of choice for the plasma-facing components in the International Thermonuclear Experimental Reactor (ITER) and DEMOnstration Power Station (DEMO)[4,5], where the strength and structural integrity play a critical role with respect to the durable and safe exploitation of the reactor

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Summary

Introduction

Precipitation strengthening is of great technological importance to engineer materials with the required strength. Tungsten (W) based alloys are known to harden and embrittle as a result of irradiation-assisted transmutation to rhenium (Re) and its subsequent precipitation into non-coherent precipitates. Thereby the impact of precipitate shape, size, interspacing and composition is assessed Based on those results, an analytical model to predict precipitation hardening of σ, χ and hcp phase particles in bcc W is proposed and compared to available experimental data from mechanical tests on irradiated materials. Following the preliminary design assessment of DEMO, after the first 5 years of full power operation, a few percent (3–6%) of Re will form in W on both first wall and divertor components[12] This concentration is well below the solubility limit, the irradiation-induced and –enhanced diffusion will cause the precipitation of Re, which was observed in fission irradiation experiments[9,10,11]. Experimentalists call for a theoretical assessment of the interaction of nano-scale Re-rich precipitates with dislocations to progress our fundamental understanding of the performance of W under fusion operating conditions

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