Designing Advanced Ceramic Waste Forms for Electrochemical Processing Salt Waste

2016 ◽  
Author(s):  
W. L. Ebert ◽  
C. T. Snyder ◽  
Steven Frank ◽  
Brian Riley
Keyword(s):  
Electrochemical Processing ◽  
Ceramic Waste ◽  
Advanced Ceramic ◽  
Waste Forms ◽  
Salt Waste

scholarly journals Compositional control of radionuclide retention in hollandite‐based ceramic waste forms for Cs‐immobilization

2018 ◽  
Vol 102 (7) ◽  
pp. 4314-4324 ◽  
Author(s):  
Mingyang Zhao ◽  
Yun Xu ◽  
Lindsay Shuller‐Nickles ◽  
Jake Amoroso ◽  
Anatoly I. Frenkel ◽  
...  
Keyword(s):  
Ceramic Waste ◽  
Waste Forms ◽  
Compositional Control

Aging Studies of Pu-238 and -239 Containing Calcium Phosphate Ceramic Waste-forms

2013 ◽  
Vol 1518 ◽  
pp. 73-78 ◽  
Author(s):  
Shirley K. Fong ◽  
Brian L. Metcalfe ◽  
Randall D. Scheele ◽  
Denis M. Strachan
Keyword(s):  
Calcium Phosphate ◽  
Accelerated Aging ◽  
Waste Form ◽  
Calcium Phosphate Ceramic ◽  
Ceramic Waste ◽  
Waste Forms ◽  
Aging Studies ◽  
Flow Through ◽  
Pyrochemical Reprocessing

ABSTRACTA calcium phosphate ceramic waste-form has been developed at AWE for the immobilisation of chloride containing wastes arising from the pyrochemical reprocessing of plutonium. In order to determine the long term durability of the waste-form, aging trials have been carried out at PNNL. Ceramics were prepared using Pu-239 and -238, these were characterised by PXRD at regular intervals and Single Pass Flow Through (SPFT) tests after approximately 5 yrs.While XRD indicated some loss of crystallinity in the Pu-238 samples after exposure to 2.8 x 1018 α decays, SPFT tests indicated that accelerated aging had not had a detrimental effect on the durability of Pu-238 samples compared to Pu-239 waste-forms.

scholarly journals Corrosion tests with uranium- and plutonium-loaded ceramic waste forms.

2003 ◽  
Author(s):  
L R Morss ◽  
S G Johnson ◽  
W L Ebert ◽  
T DiSanto ◽  
S M Frank ◽  
...  
Keyword(s):  
Corrosion Tests ◽  
Ceramic Waste ◽  
Waste Forms

scholarly journals Challenges in Modeling the Degradation of Ceramic Waste Forms

2011 ◽  
Author(s):  
Ramaswami Devanathan ◽  
Fei Gao ◽  
Xin Sun
Keyword(s):  
Ceramic Waste ◽  
Waste Forms

Progress on Ongoing Waste form HIP projects at ANSTO

MRS Advances ◽  
2018 ◽  
Vol 3 (20) ◽  
pp. 1059-1064 ◽  
Author(s):  
Eric R. Vance ◽  
Dorji T. Chavara ◽  
Daniel J. Gregg
Keyword(s):  
Spent Nuclear Fuel ◽  
Technology Development ◽  
Hot Isostatic Pressing ◽  
Waste Form ◽  
Process Technology ◽  
Ceramic Waste ◽  
Waste Forms ◽  
Produce Glass ◽  
Form Development ◽  
Year 2000

Abstract:Since the year 2000, Synroc has evolved from the titanate full-ceramic waste forms developed in the late 1970s to a hot isostatic pressing (HIP) technology platform that can be applied to produce glass, glass–ceramic, and ceramic waste forms and where there are distinct advantages over vitrification in terms of, for example, waste loading and suppressing volatile losses. This paper describes recent progress on waste form development for intermediate-level wastes from 99Mo production at ANSTO, spent nuclear fuel, fluoride pyroprocessing wastes and 129I. The microstructures and aqueous dissolution results are presented where applicable. This paper provides perspective on Synroc waste forms and recent process technology development in the nuclear waste management industry.

Ceramic Waste Forms

2020 ◽  
pp. 445-466
Author(s):  
Eric R. Vance ◽  
Yingjie Zhang ◽  
Daniel J. Gregg
Keyword(s):  
Ceramic Waste ◽  
Waste Forms

U and Pu Liii XAFS of Pu-doped glass and ceramic waste forms

1998 ◽  
Vol 271-273 ◽  
pp. 240-243 ◽  
Author(s):  
N.J Hess ◽  
W.J Weber ◽  
S.D Conradson
Keyword(s):  
Ceramic Waste ◽  
Waste Forms ◽  
Doped Glass
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