scholarly journals CRYSTALLINE CERAMIC WASTE FORMS: REFERENCE FORMULATION REPORT

2012 ◽  
Author(s):  
K. Brinkman ◽  
K. Fox ◽  
J. Marra
1988 ◽  
Vol 127 ◽  
Author(s):  
A. G. Solomaha ◽  
Hj. Matzkeb

ABSTRACTThe leaching performance of pressureless sintered SYNROC crystalline ceramic waste forms containing simulated high-level radioactive waste has been evaluated under different leach conditions, i.e. in deionized water and in a simulated brine (Q-brine) at different leach temperatures. The leach solutions were analyzed using inductively coupled plasma and atomic absorption spectrometry (ICPS and AAS) to determine the concentrations of the simulated waste elements and the matrix components released into the leachants. The leach rates of Ba and Ca were in the range of 0.1 to 0.02 g/(m2.d) after one week of leaching in deionized water at 150 °C. No significant difference in the leach behaviour of SYNROC was observed in distilled water and in simulated brine. The leached surfaces of SYNROC were characterized using Rutherford backscattering spectrometry (RBS), secondary ion mass spectrometry (SIMS), scanning electron microscopy (SEM) and elastic recoil detection analysis (ERDA). RBS and SIMS analyses revealed the existence of near-surface layers enriched in Ti and depleted in Ba and Ca. Elastic recoil detection analysis showed the existance of hydrated surface layers on the leached SYNROC which were much thinner than those observed in parallel work with borosilicate waste glasses. Radiation damage produced by ion implantation increased the otherwise very-small leach rates of SYNROC. At high damage levels, SYNROC was shown to become amorphous (metamict).


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

2013 ◽  
Vol 1518 ◽  
pp. 73-78 ◽  
Author(s):  
Shirley K. Fong ◽  
Brian L. Metcalfe ◽  
Randall D. Scheele ◽  
Denis M. Strachan

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.


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