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Zuojiang Wang

xia men university

H指数:4

被引数:30

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Effect of Si content on dislocation loop evolution and hardening behavior of irradiated Al-Mg-Si alloys

Si含量对辐照Al-Mg-Si合金位错环演化和硬化行为的影响

Journal of Nuclear Materials

IF3.2

2025-11-090

PRE

Misorientation angle-dependent anomalous preferential nucleation of dislocation loop at grain boundary in irradiated aluminum alloys

晶界处辐照铝合金中位错环的位向差依赖性异常择优形核

Acta Materialia

IF9.3

2025-11-040

PRE

In-situ simulation of transmutation-produced Si-containing precipitates of Al alloys via Si ion irradiation

通过Si离子辐照原位模拟铝合金中嬗变产生的含Si沉淀物

Journal of Nuclear Materials

IF3.2

2025-09-220

PRE

Exploring differences in irradiation-induced defects between Mg2Si and Si-rich precipitates in Al-alloys

探索Al-alloys中Mg2Si和Si-rich precipitates之间辐照诱导缺陷的差异

Journal of Nuclear Materials

IF3.2

2025-07-130

PRE

Differential effects of Si/dpa ratio on the evolution of dislocation loops in Al-2.64 Mg alloy during in-situ irradiation

Si/dpa比率对Al-2.64 Mg合金在原位辐照过程中位错环演化产生的差异影响

Journal of Nuclear Materials

IF3.2

2025-07-080

PRE

Ordered distribution of bubble complexes induced by the planar defects

由平面缺陷引起的气泡复合体的有序分布

Journal of the European Ceramic Society

IF6.2

2025-05-270

PRE

Analysis of the variation in mechanical properties of α- and β-SiC under high-temperature Si-ion irradiation

CERAMICS INTERNATIONAL

IF5.6

2024-10-011

PRE

In-situ investigation of helium effect on diverse precipitate/matrix interface areas in irradiated 5052 aluminum alloy

SURFACES AND INTERFACES

IF6.3

2024-08-011

PRE

Effect of temperature on the anisotropic distribution of defects in self-ion irradiated α-SiC: In-situ TEM investigation

CERAMICS INTERNATIONAL

IF5.6

2023-12-012

PRE

Evolution and characteristics of defect clusters in H2 thorn irradiated Al- based Gd2O3-W composites used as spent fuel shielding materials

MATERIALS TODAY ENERGY

IF8.6

2023-06-011

PRE