Influence of Inhomogeneity Nucleation on Radiation-induced Microstructural Evolution in Tungsten by Cluster Dynamics Method

被引：0

作者：

Wu S. ^{[1
]}

Liu L. ^{[2
]}

Deng H. ^{[2
]}

He X. ^{[1
]}

Wang D. ^{[1
]}

Cao J. ^{[1
]}

Yang W. ^{[1
]}

机构：

[1] Division of Reactor Engineering Technology Research, China Institute of Atomic Energy, Beijing

[2] Hunan University, Changsha

来源：

Yuanzineng Kexue Jishu/Atomic Energy Science and Technology | 2021年 / 55卷 / 07期

关键词：

Cluster dynamics; Microstructure evolution; Radiation damage; Tungsten;

D O I：

10.7538/yzk.2021.youxian.0085

中图分类号：

学科分类号：

摘要：

Tungsten (W) and its alloys are the most prospective plasma facing materials (PFMs) in future fusion reactors. The service performance of W and its alloys directly affects the safety of fusion reactors in long-term service. Irradiation-induced microstructure evolution of W and its alloys leads to the irradiation embrittlement phenomenon, which is always the key factor limiting its engineering application. In this paper, based on the molecular dynamics calculation results, the cluster dynamics model was improved for modeling the irradiation-induced microstructural evolution behavior of materials. A more complete physical model to describe the generation behavior of radiation defects in materials was adopted, and the influence of the generation process of radiation defects in W matrix on the microstructural evolution behavior was explored. The simulation results show that the defect clusters directly generated by cascade collisions induced by high energy primary displacement atom (PKA) are the most important nucleation mechanism in the evolution of dislocation loops and cavities in W. The diffusion behavior of interstitial clusters caused by heterogeneous nucleation has an important influence on the growth behavior of dislocation loops, resulting in the appearance of sub-spikes and step morphology in the size distribution of dislocation loops. © 2021, Editorial Board of Atomic Energy Science and Technology. All right reserved.

引用

页码：1241 / 1252

页数：11

共 26 条

[1]

PITTS A R, CARPENTIER S, ESCOURBIAC F, Et al., Physics basis and design of the ITER plasma-facing components, Journal of Nuclear Materials, 415, 1, pp. S957-S964, (2011)

[2]

KNASTER J, MOESLANG A, MUROGA T., Materials research for fusion, Nature Physics, 12, 5, pp. 424-434, (2016)

[3]

ZINKLE S J., Fusion materials science: Overview of challenges and recent progress, Physics of Plasmas, 12, 5, (2005)

[4]

KONINGS R, PINTSUK G., Tungsten as a plasma-facing material, Comprehensive Nuclear Materials, 4, pp. 551-581, (2012)

[5]

RAJ R, ASHBY M F., Intergranular fracture at elevated temperature, Acta Metallurgica, 23, 6, pp. 653-666, (1975)

[6]

YOSHIDA N., Microstructure formation and its role on yield strength in AISI 316 SS irradiated by fission and fusion neutrons, Journal of Nuclear Materials, 174, 2, pp. 220-228, (1990)

[7]

SAND A E, DUDAREV S L, NORDLUND K., High energy collision cascades in tungsten: Dislocation loops structure and clustering scaling laws, Europhysics Letters, 103, 4, pp. 111-135, (2013)

[8]

CAO Han, HE Xinfu, WANG Dongjie, Et al., Molecular dynamics simulation of displacement cascades in α-iron at different temperatures, Atomic Energy Science and Technology, 53, 3, pp. 487-493, (2019)

[9]

YI X, SAND A E, MASON D R, Et al., Direct observation of size scaling and elastic interaction between nano-scale defects in collision cascades, Europhysics Letters, 110, 3, (2015)

[10]

El-ATWANI O, LI N, LI M, Et al., Outstanding radiation resistance of tungsten-based high entropy alloys, Science Advances, 5, 3, (2019)

← 1 2 3 →