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Xiaoyan Shu

Southwest University of Science and Technology

H指数:24

被引数:1,468

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Optimal Si/al molar ratio achieves ultra-high CeO2 loading and enhanced stability for nuclear waste immobilization in aluminosilicate glasses

最优Si/Al摩尔比实现了在铝硅酸盐玻璃中CeO2的超高负载和稳定性增强，用于核废料固化。

Environmental Research

IF7.7

2025-09-180

PRE

Hydrothermal Synthesis and Growth of Stable Strontium Apatite for Radioactive Salt Waste Immobilization

水热合成与生长用于放射性盐类废物固化的稳定锶磷灰石

Journal of Solid State Chemistry

IF3.5

2025-09-080

PRE

Synergistic immobilization of complex TRPO-CS nuclear waste by natural mineral materials: Glass and CsAlSiO4 dominant glass-ceramics

天然矿物材料对复合TRPO-CS核废料的协同固定：玻璃和CsAlSiO4主导的玻璃陶瓷

Ceramics International

IF5.6

2025-06-250

PRE

In situ growth of N-doped bamboo-like carbon nanotubes embedded with FeNi nanoparticles on carbon cloth as self-standing cathodes for efficient rechargeable zinc-air batteries

CATALYSIS SCIENCE & TECHNOLOGY

IF4.2

2025-01-010

PRE

Multiphase synergistic immobilization of complex trialkyl phosphine oxide end-waste into an iron-containing aluminosilicate glass-ceramic

JOURNAL OF MATERIALS SCIENCE & TECHNOLOGY

IF14.3

2024-06-014

PRE

Research on the Properties of Wasteforms after Direct Involvement of Uranium-Containing Silica Gel in Glass Network Formation

INORGANIC CHEMISTRY

IF4.7

2024-03-140

PRE

Converting natural metamorphic granite and simulated actinide oxide to aluminosilicate glass for nuclear waste immobilization

CERAMICS INTERNATIONAL

IF5.6

2023-11-012

PRE

Structure and performance sensitivity to simulated An4+ waste doping in a high-silicon glasses-ceramics

MATERIALS SCIENCE AND ENGINEERING B-ADVANCED FUNCTIONAL SOLID-STATE MATERIALS

IF4.6

2023-06-014

PRE

Crystallization behavior of uranium glass-ceramic matrix under simulated self-irradiation conditions

JOURNAL OF NON-CRYSTALLINE SOLIDS

IF3.5

2023-01-011

PRE

A natural granite based glass-ceramics matrix for immobilizing simulated An3+waste

JOURNAL OF NON-CRYSTALLINE SOLIDS

IF3.5

2023-01-015

OAAI

Immobilization mechanism of Gd2Zr2O7 ceramic for nuclear waste treatment

CERAMICS INTERNATIONAL

IF5.6

2022-12-019

PRE

Experimentally and Theoretically Revealing the Co-Doping Effects of Ce-Sr in Gd2Zr2O7

IF3.9

2022-09-133

PRE

Effective management of trialkyl phosphine oxides waste via Gd2Zr2O7 ceramic

JOURNAL OF CLEANER PRODUCTION

IF10

2022-05-017

PRE

Immobilization of simulated An3+ into synthetic Gd2Zr2O7 ceramic by SPS without occupation or valence design

CERAMICS INTERNATIONAL

IF5.6

2021-03-0115

PREAI

Heavy-ion irradiation effects on uranium-contaminated soil for nuclear waste

JOURNAL OF HAZARDOUS MATERIALS

IF11.3

2021-03-0123

PREAI

Effect of improved trialkyl phosphine oxides waste content on phase composition and density of spark plasma sintered Gd2Zr2O7 ceramics

INTERNATIONAL JOURNAL OF ENERGY RESEARCH

IF4.2

2021-01-186

OA

Microwave vitrification of simulated radioactively contaminated soil: Mechanism and performance

JOURNAL OF SOLID STATE CHEMISTRY

IF3.5

2021-01-0116

PREAI

Rapid vitrification of uranium-contaminated soil: Effect and mechanism

ENVIRONMENTAL POLLUTION

IF7.3

2020-08-0146

PREAI

Immobilization of simulated waste into pure Gd2Zr2O7 pyrochlore without space occupancy design

JOURNAL OF THE AMERICAN CERAMIC SOCIETY

IF3.8

2020-04-286

PREAI

Solubility of Nd3+ and Ce4+ in co-doped simulated radioactive contaminated soil after microwave vitrification

CERAMICS INTERNATIONAL

IF5.6

2020-04-0118

PREAI