Hardening effect of multi-energyW2+-ion irradiation on tungsten–potassium alloy

doi:10.1088/1674-1056/ab9c09

Abstract

Tungsten is one of the most promising plasma-facing materials (PFMs) to be used in the nuclear fusion reactor as divertor material in the future. In this work, W²⁺-ions bombardment is used to simulate the neutron irradiation damage to commercial pure tungsten (W) and rolled tungsten–potassium (W–K). The 7 MeV of 3 × 10¹⁵ W²⁺-ions/cm², 3 MeV of 4.5 × 10¹⁴ W²⁺, and 2 MeV of 3 × 10¹⁴ W²⁺-ions/cm² are applied at 923 K in sequence to produce a uniform region of 100 nm–400 nm beneath the sample surface with the maximum damage value of 11.5 dpa. Nanoindentation is used to inspect the changes in hardness and elastic modulus after self-ion irradiation. Irradiation hardening occurred in both materials. The irradiation hardening of rolled W–K is affected by two factors: one is the absorption of vacancies and interstitial atoms by potassium bubbles, and the other is the interaction between potassium bubbles and dislocations. Under the condition of 11.5 dpa, the capability of defect absorption can reach a threshold. As a result, dislocations finally dominate the hardening of rolled W–K. Specific features of dislocation loops in W–K are further observed by transmission electron microscopy (TEM) to explain the hardening effect. This work might provide valuable enlightenment for W–K alloy as a promising plasma facing material candidate.

Keywords: plasma facing material tungsten-potassium alloy ion-irradiation hardening nanoindentation

Received: 24 February 2020
Revised: 28 May 2020
Accepted manuscript online: 12 June 2020

PACS:	52.55.Rk	(Power exhaust; divertors)
	61.80.Jh	(Ion radiation effects)
	28.52.Fa	(Materials)

Corresponding Authors: ^†Corresponding author. E-mail: kzhang@scu.edu.cn ^‡Corresponding author. E-mail: tangjun@scu.edu.cn

About author:

†Corresponding author. E-mail: kzhang@scu.edu.cn

‡Corresponding author. E-mail: tangjun@scu.edu.cn

* Project supported by the National Natural Science Foundation of China (Grant Nos. 11975160 and 11775149). One of the authors, Kun Zhang, was supported by the Fundamental Research Funds for the Central Universities, China.

Cite this article:

Yang-Yi-Peng Song(宋阳一鹏), Wen-Bin Qiu(邱文彬), Long-Qing Chen(陈龙庆), Xiao-Liang Yang(杨晓亮), Hao Deng(邓浩), Chang-Song Liu(刘长松), Kun Zhang(张坤)†, and Jun Tang(唐军)‡ Hardening effect of multi-energy^W2+-ion irradiation on tungsten–potassium alloy 2020 Chin. Phys. B 29 105202

Fig. 1.

Schematic diagram of spark plasma sintering (SPS) device.

Fig. 2.

Damage profiles of self-ion implantation calculated by SRIM mode.

Fig. 3.

Nanoindentation measured load displacement curves for pure tungsten and rolled W–K before and after irradiation.

Fig. 4.

Hardness versus displacement for (a) rolled W–K and (b) pure W, showing an increase in hardness after self-ion irradiation.

Fig. 5.

Hardness decreasing with displacement increasing for rolled W–K and pure W after self-ion implanted.

Fig. 6.

Load–diaplacement² (P–δ²) curves for (a) pure W and (c) rolled W–K, unirradiated and irradiated. Gradient (K) of P–δ² lines (b) in panel (a) and (d) in panel (c) versus displacement.

Fig. 7.

TEM images of dislocation loops in pure W and rolled W–K irradiated to 11.5-dpa damage (TEM bright field images): (a) unirradiated W–K; (b) 11.5-dpa region of rolled W–K; (c) DAR of rolled W–K; (d) 11.5-dpa region of pure W; (e) DAR of pure W. All images have the same scale bar of 100 nm. Red arrow points to top surface of sample, and white box highlighting area enlarged shows dislocation loops of around 15 nm in size.

Fig. 8.

(a) Surface morphology of pure W unirradiated. (b) Surface morphology of pure W irradiated. (c) Surface morphology of rolled W–K unirradiated. (d) Surface morphology of rolled W–K irradiated.

Fig. 9.

(a) Elasticity moduli of pure tungsten and rolled W–K alloy samples. (b) XRD spectra of tungsten self-ions irradiated samples with black line representing the pure tungsten after being irradiated, red line the pure tungsten before being irradiated, blue line the W–K alloy after being irradiated, and green line the W–K alloy before being irradiated.

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Hardening effect of multi-energy^W2+-ion irradiation on tungsten–potassium alloy