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Invited speakers

Name

Abstract title

Affiliation

Country

Emilien Sauvage

Advancements in High-Level Radioactive Waste Vitrification in France: A Comparative Analysis of Inductive Hot Metallic Melter (IHMM) and Cold Crucible Inductive Melter (CCIM) Technologies with a Focus on Platinum Group Metals (PGM) Behavior

CEA

France

Haibo Peng
(彭海波)

Influence of Irradiation of Xe and He Ions on Leaching Behaviors of Borosilicate Glasses

Lanzhou University

China

Jaroslav Klouzek

Kinetics of Refractory Corrosion During Waste Glass Melting

University of Chemistry and Technology Prague

Czech Republic

John McCloy

Hanford Glass Composition-Structure-Property-Processing Relations

Washington State University

US

Julien Delrieu

Vitrification of R&D High Activity Acidic Solutions in ATALANTE Facility

CEA

France

Lang Wu
(吴浪)

Controlling of yellow phase during high-level liquid waste vitrification process

Southwest University of Science and Technology

China

Liyan Zhang
(张丽艳)

Investigation of HLW iron phosphate solidification glass demonstrated by CCIM platform

Shanghai Institute of Optics and Fine Mechanics

China

Luiz Pereira

Rheology of Nuclear Waste Melts: Review & Analyses

Ludwig Maximilians University (LMU) Munich

Germany

Michael Ojovan

Viscous Flow and Crossover Temperatures in Glass Forming Systems

Wuhan University of Technology

China

Qiu Li
 
(李秋)

A high-level liquid waste glass-ceramic waste form derived from ceramizable geopolymer

Wuhan University of Technology

China

Richard Pokorny

Development of mathematical modeling of cold cap for JHCM

Effect of Melter Feed Composition on the Retention of Re and Tc during Vitrification of Nuclear Waste

University of Chemistry and Technology Prague

Czech Republic

Richard Pokorny

Development of mathematical modeling of cold cap for JHCM

Effect of Melter Feed Composition on the Retention of Re and Tc during Vitrification of Nuclear Waste

University of Chemistry and Technology Prague

Czech Republic

Sandrine Miro

Self-irradiation Effects in Glass-ceramic Matrices for Radioactive Waste Immobilization

CEA

France

Shenghen Tan
(谭盛恒)

Research progress in nuclear waste vitrification at China Institute of Atomic Energy

China Insititute of Atomic Energy

China

Sophie Schuller

Insights into Liquid-Liquid Phase Separation in Nuclear Waste Glass: A Combined Experimental-Numerical Approach

CEA

France

Tetsuji Yano

Briquet Feeding Form of Glass Powder and Its Melting Behavior with Simulated High-level Radioactive Nuclear Liquid Waste from Nuclear Power Plants

Institute of Science Tokyo

Japan

Yingju Li
 (
李应举)

Corrosion Behavior and Mechanism of Inconel Alloys in Molten Glasses

Institute of Metal Research, Chinese Academy of Sciences

China

Zhiliang Chen
(陈志良)

Geochemical and Kinetic Modeling for Assessing the Leaching of Hazardous Waste-Vitrified Glasses

Chongqing University

China

Zhongzhao Li
(李忠镝)

Research Progress on China's Cold Crucible Vitrification Engineering

China Nuclear Power Engineering Co., Ltd.

China


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