Decreased surface blistering and deuterium retention in potassium-doped tungsten exposed to deuterium plasma following ion irradiation

被引：10

作者：

Ma, Xiaolei ^{[1
]}

Zhang, Xiaoxin ^{[1
]}

Wang, Ting ^{[2
]}

Gao, Yuan ^{[3
]}

Yuan, Yue ^{[2
]}

Cheng, Long ^{[2
]}

Zhu, Jipeng ^{[4
]}

Lv, Wei ^{[5
]}

Lang, Shaoting ^{[6
]}

Ge, Changchun ^{[1
]}

Yan, Qingzhi ^{[1
]}

机构：

[1] Univ Sci & Technol Beijing, Inst Nucl Mat, Sch Mat Sci & Engn, Xueyuan Rd 30, Beijing 100083, Peoples R China

[2] Beihang Univ, Sch Phys, Beijing 100191, Peoples R China

[3] Peking Univ, State Key Lab Nucl Phys & Technol, Beijing 100871, Peoples R China

[4] Sci & Technol Surface Phys & Chem Lab, Jiangyou 621908, Sichuan, Peoples R China

[5] North China Elect Power Univ, Inst Adv Mat, 2 Beinong Rd, Beijing 102206, Peoples R China

[6] Xinxiang Univ, Mech & Elect Engn, Xinxiang 453000, Peoples R China

来源：

NUCLEAR FUSION | 2023年 / 63卷 / 02期

基金：

中国国家自然科学基金;

关键词：

potassium-doped tungsten alloy; iron ion irradiation; deuterium plasma exposure; surface blistering; deuterium retention; MECHANICAL-PROPERTIES; THERMAL-SHOCK; NANOCRYSTALLINE TUNGSTEN; TANTALUM ALLOYS; HEAT-TREATMENTS; BEHAVIOR; PURE; MICROSTRUCTURE; TEMPERATURE; RESISTANCE;

D O I：

10.1088/1741-4326/aca48c

中图分类号：

O35 [流体力学]; O53 [等离子体物理学];

学科分类号：

070204 ; 080103 ; 080704 ;

摘要：

A large-size potassium-doped tungsten (KW) plate with a thickness of 15 mm was fabricated via powder metallurgy technology and hot rolling. In order to appraise the irradiation resistance of KW, the surface deuterium (D) blistering and D retention were studied on Fe11+ pre-damaged (0, 0.05 and 0.5 dpa) KW and pure tungsten (PW), which were exposed to similar to 60 eV and similar to 5 x 10(21) m(-2) s(-1) D plasmas at 500 K at a fluence of similar to 5.76 x 10(25) m(-2). The results indicate that the KW alloy can better inhibit the generation of vacancy defects after Fe11+ ion damage compared with PW because K bubbles can restrain the migration of W self-interstitial atoms and the accumulation of vacancies caused during Fe11+ ion irradiation. The Fe11+ ion pre-damage can relieve the surface blistering and D retention of PW and KW at the same time, and the KW has a better effect of inhibiting D retention, while it does not show a significant advantage in inhibiting surface blistering compared with PW. In addition, the causes of the discrepancy in total D retention and the surface morphology evolution of PW and KW are discussed in detail.

引用

页数：14

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