High-Level Radioactive Waste Glass Synthesis at Low Temperatures

1984 ◽  
Vol 67 (2) ◽  
pp. 221-227 ◽  
Author(s):  
Naohito Uetake ◽  
Yoshihiro Ozawa ◽  
Makoto Kikuchi
Keyword(s):  
Radioactive Waste ◽  
Low Temperatures ◽  
Waste Glass ◽  
High Level Radioactive Waste ◽  
High Level

scholarly journals High Level Radioactive Waste Glass Production and Product Description

1993 ◽  
Vol 333 ◽  
Author(s):  
James F. Sproull ◽  
Sharon L. Marra ◽  
Carol M. Jantzen
Keyword(s):  
Phase Separation ◽  
Radioactive Waste ◽  
Glass Phase ◽  
Glass Production ◽  
Waste Glass ◽  
Glass Product ◽  
High Level Radioactive Waste ◽  
The Matrix ◽  
High Level ◽  
Product Description

ABSTRACTA summary of the current state of defense high-level radioactive waste in the U.S. is presented. Reasons for the selection of borosilicate glass as the matrix for the waste glass product over other glasses is enunciated. The product and processing requirements which the waste glass must meet are summarized. Finally the effects of crystallization and glass-in-glass phase separation on waste glass durability are discussed. Crystallization, under typical cooling conditions, has minimal effect on durability but glass-in-glass phase separation should be avoided.

Viscoplasticity of simulated high-level radioactive waste glass containing platinum group metal particles

2014 ◽  
Vol 452 (1-3) ◽  
pp. 419-424 ◽  
Author(s):  
Kazuyoshi Uruga ◽  
Tsuyoshi Usami ◽  
Takeshi Tsukada ◽  
Satoshi Komamine ◽  
Eiji Ochi
Keyword(s):  
Radioactive Waste ◽  
Platinum Group Metal ◽  
Waste Glass ◽  
Metal Particles ◽  
High Level Radioactive Waste ◽  
Group Metal ◽  
Platinum Group ◽  
High Level

scholarly journals Chemical Analysis of High-Level Radioactive Waste Glass by ICP-AES.

1998 ◽  
Vol 14 (2) ◽  
pp. 389-394 ◽  
Author(s):  
Tsunetaka BANBA ◽  
Hiromichi HAGIYA ◽  
Yukito TAMURA ◽  
Muneaki SENOO ◽  
Chushiro YONEZAWA ◽  
...  
Keyword(s):  
Chemical Analysis ◽  
Radioactive Waste ◽  
Waste Glass ◽  
High Level Radioactive Waste ◽  
High Level

scholarly journals Chemical analysis of simulated high-level radioactive waste glass by ICP-AES and AAS.

1993 ◽  
Vol 42 (5) ◽  
pp. 317-323 ◽  
Author(s):  
Tsunetaka BANBA ◽  
Hiromichi HAGIYA ◽  
Yukito TAMURA ◽  
Chushiro YONEZAWA
Keyword(s):  
Chemical Analysis ◽  
Radioactive Waste ◽  
Waste Glass ◽  
High Level Radioactive Waste ◽  
High Level

scholarly journals Recovery of Metals from Simulated High-Level Radioactive Waste Glass through Phase Separation

2008 ◽  
Vol 45 (9) ◽  
pp. 889-898 ◽  
Author(s):  
Kazuyoshi URUGA ◽  
Kunio DOKA ◽  
Kayo SAWADA ◽  
Youichi ENOKIDA ◽  
Ichiro YAMAMOTO
Keyword(s):  
Phase Separation ◽  
Radioactive Waste ◽  
Waste Glass ◽  
High Level Radioactive Waste ◽  
High Level

Migration Behavior of Multivalent Radionuclides From Fully Radioactive Waste Glass in Compacted Sodium Bentonite

2010 ◽  
Vol 1265 ◽  
Author(s):  
Kenso Fujiwara ◽  
Kazuki Iijima ◽  
Seiichiro Mitsui ◽  
Makoto Odakura ◽  
Yukitoshi Kohara ◽  
...  
Keyword(s):  
Radioactive Waste ◽  
Diffusion Model ◽  
Waste Glass ◽  
Migration Behavior ◽  
Sodium Bentonite ◽  
Aerobic Conditions ◽  
One Dimensional ◽  
High Level Radioactive Waste ◽  
Dimensional Diffusion ◽  
High Level

AbstractIn a repository of high-level radioactive waste, radionuclides will leach from the waste glass and migrate into the surrounding bentonite after very long time. These processes occur simultaneously in the bentonite and should be evaluated to confirm the reliability of individual models and data for the performance assessment of high-level radioactive waste repository.Previous study [1] reported the results of the in-diffusion experiments of Cs in compacted sodium bentonite (Kunigel V1®) in contact with fully radioactive waste glass for 15 to 300 days under aerobic conditions. And Cs migration was successfully interpreted using fundamental one dimensional diffusion model. However, migration of other radionuclides in fully radioactive waste glass were extremely slow because of low solubility, low effective diffusivity and high distribution ratio, especially multivalent elements of actinide and lanthanide.In this study, the similar in-diffusion experiment reported by Ashida et al. [1] was carried out for about 15 years to evaluate the migration behavior of multivalent actinide and lanthanide elements. The bentonite was compacted into a stainless steel cell with 20 mm in diameter and 18 mm in length to produce dry densities of 0.5 and 1.0 Mg m-3saturated distilled water. The form of fully radioactive waste glass was borosilicate glass by using vitrified in CPF (Chemical Processing Facility). The glass sample was sliced into the disc with 4 mm in thickness and sandwiched by two pieces of the saturated bentonite sample in the diffusion cell under aerobic conditions. After 15 years, bentonite sample was sliced and immersed into the HNO3 to extract the radionuclides from the bentonite. Then profiles of Cs, Eu, Pu, Am and Cm in the bentonite sample were evaluated. The concentration profile of Cs in the bentonite was constant due to its high diffusivity.The experimental concentrations of Am, Cm and Eu in contact with compacted sodium bentonite were good agreement with the solubilities calculated by thermodynamic data. On the other hand, the profiles of Am and Cm show two parts with different slopes which cannot be fitted by simple one-dimensional diffusion model considering single specie. Leaching and migration behavior of radio nuclides will be discussed based on the one-dimensional diffusion model considering other mechanism of several species.[1] T. Ashida, et al. Migration behavior of cesium released from fully radioactive waste glass in compacted sodium bentonite. PNC Technical Report, TN8410 98-014(1998).

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