Application of electrochemical methods in the development of models for fuel dissolution and container corrosion under nuclear waste disposal conditions

1997 ◽  
Vol 75 (11) ◽  
pp. 1566-1584 ◽  
Author(s):  
D.W. Shoesmith ◽  
W.H. Hocking ◽  
B.M. Ikeda ◽  
F. King ◽  
J.J. Noël ◽  
...  
Keyword(s):  
Nuclear Fuel ◽  
Anodic Dissolution ◽  
Nuclear Waste ◽  
Chloride Solutions ◽  
Long Term Stability ◽  
Waste Container ◽  
Transport Barriers ◽  
Long Term Performance ◽  
Term Performance

The permanent disposal of nuclear fuel wastes requires the development of models that can assess the performance of a disposal vault over long periods of time. Models to assess the long-term stability of the nuclear fuel (UO2) and the corrosion performance of the waste container (either copper or titanium) have been based on electrochemical principles. Here we review the chemical/electrochemical performance of fuel and the two candidate container materials, and describe some of the electrochemical studies undertaken either to develop the mechanistic understanding upon which these models are based or to measure the values of parameters required to evaluate long-term performance. These include the following: the anodic dissolution of UO2; the reduction of O2 on various specimens of UO2; the crevice corrosion of various titanium alloys; the impedance characteristics of passive films on Ti alloys; the anodic dissolution of copper in chloride solutions; the reduction of O2 on copper; the effect of various transport barriers on the corrosion of copper; and the prediction of the corrosion potential of copper in aerated chloride solutions. Keywords: uranium dioxide, copper, titanium, nuclear waste, oxygen.

Materials Research in Nuclear Waste Management: Reflections on Twenty-Five MRS Symposia

2002 ◽  
Vol 713 ◽  
Author(s):  
Rodney C. Ewing
Keyword(s):  
Waste Management ◽  
Nuclear Waste ◽  
Scientific Basis ◽  
Nuclear Waste Management ◽  
The Past ◽  
Materials Research ◽  
Long Term Performance ◽  
Term Performance ◽  
Selection Of

ABSTRACTThe MRS symposium, “Scientific Basis for Nuclear Waste Management” was first held in Boston, November 28th to December 1st, 1978. This symposium marks the twenty-fifth in a series that now rotate to meeting sites around the world. During the past 24 years, there has been considerable progress in the development and understanding of the behavior of materials that are used in the processing, transport, containment and disposal of radioactive waste. The design and selection of materials for long-term performance has required a uniquely interdisciplinary effort. Over the same period, there have been important developments in the regulatory framework that guides the scientific and engineering needs of nuclear waste management. This paper provides a subjective commentary on the major developments and innovations during the past 25 symposia. The future challenge will be the proper and constructive integration of the science into the development of nuclear waste disposal strategies.

The Long-Term Performance of Nuclear Waste Forms: Natural Materials - Three Case Studies

1992 ◽  
Vol 294 ◽  
Author(s):  
Rodney C. Ewing
Keyword(s):  
Case Studies ◽  
Nuclear Waste ◽  
Experimental Results ◽  
Waste Form ◽  
Short Term ◽  
Waste Forms ◽  
Long Term Performance ◽  
Term Performance ◽  
Nuclear Waste Forms

ABSTRACTNatural materials may be used to advantage in the evaluation of the long-term performance of nuclear waste forms. Three case studies are presented: (I) radiation effects in ceramic waste forms; (II) corrosion products of U02 under oxic conditions; (III) corrosion rate of nuclear waste glasses. For each case, a natural phase which is structurally and chemically analogous to the waste form is identified and used to evaluate the long-term behavior of a nuclear waste form. Short-term experimental results are compared to the observations made of analogous natural phases. The three case studies illustrate that results may range between providing fundamental data needed for the long-term evaluation of a waste form to only providing qualitative data of limited use. Although in the most rigorous view the long-term behaviour of a phase cannot be predicted, the correspondence between short-term experimental results and observations made of natural phases provides confidence in the “predicted” behavior of the waste form. The strength of this approach rests with the degree to which a mechanistic understanding of the phenomenon is attained.

scholarly journals Long-term stability and reusability of molecularly imprinted polymers

2017 ◽  
Vol 8 (4) ◽  
pp. 666-673 ◽  
Author(s):  
Jozsef Kupai ◽  
Mayamin Razali ◽  
Sibel Buyuktiryaki ◽  
Rustem Kecili ◽  
Gyorgy Szekely
Keyword(s):  
Molecularly Imprinted Polymers ◽  
Functional Monomer ◽  
Molecularly Imprinted ◽  
Imprinted Polymers ◽  
Adsorption Studies ◽  
Term Stability ◽  
Long Term Stability ◽  
Long Term Performance ◽  
Term Performance

The effect of crosslinker, functional monomer and extraction on the long-term performance and degradation of molecularly imprinted polymers was investigated through adsorption studies, NMR, SEM, TGA and BET.

Demonstration of a System Performance Assessment Process

1990 ◽  
Vol 212 ◽  
Author(s):  
Kenneth W. Dormuth
Keyword(s):  
Performance Assessment ◽  
Nuclear Fuel ◽  
Research Area ◽  
Assessment Process ◽  
Conceptual Engineering ◽  
Disposal Facility ◽  
Long Term Performance ◽  
Term Performance ◽  
Nuclear Fuel Waste

ABSTRACTTo help evaluate the concept of nuclear fuel waste disposal in plutonic rock of the Canadian Shield, the long-term performance of a hypothetical disposal facility is being studied. This case study uses information from a Shield research area, laboratories, and conceptual engineering. It illustrates the use of performance assessment to derive constraints on the siting, construction, and operation of a disposal facility, and to demonstrate the feasibility of safe disposal of nuclear fuel waste.

scholarly journals Sintered Glass Monoliths as New Supports for Affinity Columns

2021 ◽  
Author(s):  
Marco Wilke ◽  
Bettina Röder ◽  
Martin Paul ◽  
Michael G. Weller
Keyword(s):  
Specific Binding ◽  
Protein A ◽  
Peak Shape ◽  
Long Term Stability ◽  
Sintered Glass ◽  
One Step ◽  
Pressure Resistance ◽  
Long Term Performance ◽  
Term Performance

A novel stationary phase for affinity separations is presented. This material is based on sintered borosilicate glass readily available as semi-finished filter plates with defined porosity and surface area. The material shows fast binding kinetics and excellent long-term stability under real application conditions due to lacking macropores and high mechanical rigidity. The glass surface can be easily modified with standard organosilane chemistry to immobilize selective binders or other molecules used for biointeraction. In this paper, the manufacturing of the columns and their respective column holders by 3D printing is shown in detail. The model system protein A/IgG was chosen as an example to examine the properties of such monolithic columns under realistic application conditions. Several specifications, such as (dynamic) IgG capacity, pressure stability, long-term performance, productivity, non-specific binding, and peak shape, are presented. It could be shown that due to the very high separation speed, 250 mg antibody per hour and column can be collected, which surpasses the productivity of most standard columns of the same size. The total IgG capacity of the shown columns is around 4 mg (5.5 mg/mL), which is sufficient for most tasks in research laboratories. The cycle time of an IgG separation can be less than 1 minute. Due to the glass material's excellent pressure resistance, these columns are compatible with standard HPLC systems. This is usually not the case with standard affinity columns, limited to manual use or application in low-pressure systems. The use of a standard HPLC system also improves the ability for automation, which enables the purification of hundreds of cell supernatants in one day. The sharp peak shape of the elution leads to an enrichment effect, which might increase the concentration of IgG by a factor of 3. The final concentration of IgG can be around 7.5 mg/mL without the need for an additional nanofiltration step. The purity of the IgG was > 95% in one step and nearly 99% with a second polishing run.

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