Solubility of U(VI) in chloride solutions. I. The stable oxides/hydroxides in NaCl systems, solubility products, hydrolysis constants and SIT coefficients-Reference-Cited by-同舟云学术

Solubility of U(VI) in chloride solutions. I. The stable oxides/hydroxides in NaCl systems, solubility products, hydrolysis constants and SIT coefficients

Published:2017-11 Issue: Volume:114 Page:2-13
ISSN:0021-9614
Container-title:The Journal of Chemical Thermodynamics
language:en
Short-container-title:The Journal of Chemical Thermodynamics

Author:

Altmaier Marcus,Yalçıntaş Ezgi,Gaona Xavier,Neck Volker,Müller Regina,Schlieker Martina,Fanghänel Thomas

Publisher

Elsevier BV

Subject

Physical and Theoretical Chemistry,General Materials Science,Atomic and Molecular Physics, and Optics

Reference50 articles.

1. Solubility products and complex-formation equilibria in the systems uranyl hydroxide and uranyl carbonate at 25°C and I=0.1M;Kramerschnabel;Radiochim. Acta,1992

2. The solubility of (UO2)3(PO4)2·4H2O(s) and the formation of U(VI) phosphate complexes – their influence in uranium speciation in natural-waters;Sandino;Geochim. Cosmochim. Acta,1992

3. Behavior of U(VI) solids under conditions of natural aquatic systems;Meinrath;Inorg. Chim. Acta,1993

Cited by 38 articles. 订阅此论文施引文献订阅此论文施引文献，注册后可以免费订阅5篇论文的施引文献，订阅后可以查看论文全部施引文献

1. Experimental and computational evidence of U(VI)–OH–Si(OH)4 complexes under alkaline conditions: Implications for cement systems;Chemosphere;2024-02

2. Time-Dependent Retention of a Mixture of Cs(I), Sm(III), Eu(III) and U(VI) as Waste Cocktail by Calcium Silicate Hydrate (C-S-H) Phases;Minerals;2023-11-22

3. Significance of MOF adsorbents in uranium remediation from water;Environmental Research;2023-11

4. Beryllium solubility and hydrolysis in dilute to concentrated CaCl2 solutions: thermodynamic description in cementitious systems;Frontiers in Nuclear Engineering;2023-10-17

5. Phase analysis of simulated nuclear fuel debris synthesized using UO2, Zr, and stainless steel and leaching behavior of the fission products and matrix elements;Nuclear Engineering and Technology;2023-04