Behavior of helium cavities in ion-irradiated W-Ni-Fe ductile-phase toughened tungsten

被引：12

作者：

Jiang, Weilin ^{[1
]}

Zhang, Dalong ^{[1
]}

Li, Dongsheng ^{[1
]}

Heo, Jaeyoung ^{[1
]}

Wang, Zhiqiang ^{[2
]}

Zhang, Limin ^{[2
]}

Overman, Nicole ^{[1
]}

Varga, Tamas ^{[1
]}

Hu, Zhihan ^{[3
]}

Wang, Xuemei ^{[3
]}

Shao, Lin ^{[3
]}

Setyawan, Wahyu ^{[1
]}

机构：

[1] Pacific Northwest Natl Lab, POB 999,902 Battelle Blvd,MSIN J4-55, Richland, WA 99352 USA

[2] Lanzhou Univ, Sch Nucl Sci & Technol, Lanzhou, Gansu, Peoples R China

[3] Texas A&M Univ, Dept Nucl Engn, College Stn, TX USA

来源：

JOURNAL OF NUCLEAR MATERIALS | 2022年 / 561卷

关键词：

Helium cavity; Ion irradiation; Ductile -phase toughened tungsten; HEAVY ALLOYS; FUSION; POWER;

D O I：

10.1016/j.jnucmat.2022.153565

中图分类号：

T [工业技术];

学科分类号：

08 ;

摘要：

This study reports on the distribution of helium (He) cavities in a hot-rolled W-Ni-Fe ductile-phase toughened tungsten (DPT W) composite irradiated to a dose and a helium concentration that are comparable to those in the material after 5-year irradiation in a conceptual fusion power plant. The DPT W sample consists of W particles embedded in a ductile-phase NiFeW matrix with a nominal composition of 90W7Ni-3Fe by weight. It was hot-rolled to a thickness reduction by 87% (87R DPT W). Sequential and individual irradiations of the material with 1.2 MeV Ni + ions to a fluence of 2.15 x 10 16 Ni + /cm 2 and 90 keV He + ions to 6.5 x 10 15 He + /cm 2 was performed at 973 K. Larger He cavities with a lower number density are observed in NiFeW than W. Helium cavities are aggregated preferentially along the NiFeW/W interphase boundary. This behavior is not observed along the W/W grain boundary under the same irradiation conditions. The average corrected cavity diameter or volume appears to be smaller in the sequentially irradiated sample than He + ion irradiated sample. There is no evidence for formation of visible voids or Ni precipitates in W phase irradiated with Ni + ions only. Diffusion, clustering and trapping of vacancies and He atoms during He + ion irradiation at 973 K may be responsible for the formation of the He cavities. (c) 2022 Elsevier B.V. All rights reserved.

引用

页数：11

共 31 条

[1] Predicting the performance of tungsten in a fusion environment: a literature review [J].

Abernethy, R. G. .

MATERIALS SCIENCE AND TECHNOLOGY, 2017, 33 (04) :388-399

[2]

Agarwal S., NUCL I METH PHYS R B, V503, P11

[3] On the remarkable fracture toughness of 90 to 97W-NiFe alloys revealing powerful new ductile phase toughening mechanisms [J].

Alam, M. E. ;

Odette, G. R. .

ACTA MATERIALIA, 2020, 186 :324-340

[4]

ASTM, 2009, Annual Book of ASTM Standards, V12

[5] A density functional theory assessment of the clustering behaviour of He and H in tungsten [J].

Becquart, C. S. ;

Domain, C. .

JOURNAL OF NUCLEAR MATERIALS, 2009, 386-88 :109-111

[6] The use of tungsten in fusion reactors: A review of the hydrogen retention and migration properties [J].

Causey, RA ;

Venhaus, TJ .

PHYSICA SCRIPTA, 2001, T94 :9-15

[7] Fusion power: a challenge for materials science [J].

Duffy, D. M. .

PHILOSOPHICAL TRANSACTIONS OF THE ROYAL SOCIETY A-MATHEMATICAL PHYSICAL AND ENGINEERING SCIENCES, 2010, 368 (1923) :3315-3328

[8] Helium bubble formation in ultrafine and nanocrystalline tungsten under different extreme conditions [J].

El-Atwani, O. ;

Hattar, K. ;

Hinks, J. A. ;

Greaves, G. ;

Harilal, S. S. ;

Hassanein, A. .

JOURNAL OF NUCLEAR MATERIALS, 2015, 458 :216-223

[9] Ab initio study of helium in α-Fe:: Dissolution, migration, and clustering with vacancies -: art. no. 064117 [J].

Fu, CC ;

Willaime, F .

PHYSICAL REVIEW B, 2005, 72 (06)

[10] The influence of ion beam rastering on the swelling of self-ion irradiated pure iron at 450 °C [J].

Gigax, Jonathan G. ;

Aydogan, Eda ;

Chen, Tianyi ;

Chen, Di ;

Shao, Lin ;

Wu, Y. ;

Lo, W. Y. ;

Yang, Y. ;

Garner, F. A. .

JOURNAL OF NUCLEAR MATERIALS, 2015, 465 :343-348

← 1 2 3 4 →