Chemical and mineralogical modifications of simplified radioactive waste calcine during heat treatment-Reference-Cited by-同舟云学术

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Chemical and mineralogical modifications of simplified radioactive waste calcine during heat treatment

Published:2014-05 Issue:1-3 Volume:448 Page:8-19
ISSN:0022-3115
Container-title:Journal of Nuclear Materials
language:en
Short-container-title:Journal of Nuclear Materials

Author:

Monteiro A.,Schuller S.,Toplis M.J.,Podor R.,Ravaux J.,Clavier N.,Brau H.P.,Charpentier T.,Angeli F.,Leterrier N.

Publisher

Elsevier BV

Subject

Nuclear Energy and Engineering,General Materials Science,Nuclear and High Energy Physics

Reference42 articles.

1. Glass matrices for immobilizing nuclear waste containing molybdenum and phosphorus

2. Development of glasses for the vitrification of high level liquid waste (HLLW) in a joule heated ceramic melter

3. Vitrification and testing of a Hanford high-level waste sample. Part 1: Glass fabrication, and chemical and radiochemical analysis

4. Barium borosilicate glass – a potential matrix for immobilization of sulfate bearing high-level radioactive liquid waste

5. Effect of Alumina Source on the Rate of Melting Demonstrated with Nuclear Waste Glass Batch

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1. Formation Mechanism and Structural Characterization of NaAl11O17 Based on Solid-State Reaction;JOM;2024-08-06

2. Research on calcination thermal decomposition process of simulated high-level liquid waste based on two-step vitrification;Nuclear Engineering and Design;2024-08

3. Research on Calcination Thermal Decomposition Process of High-Level Liquid Waste Based on Two-Step Vitrification;2024

4. Research on Calcination Thermal Decomposition Process of High-Level Liquid Waste Based on Two-Step Vitrification;2024

5. Precipitation behaviour of simulated high-level liquid waste during the denitration process based on two-step vitrification;Nuclear Engineering and Design;2023-12

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