High-Level Production and Long-Term Storage of Engineered Antibodies in Transgenic Tobacco Seeds

1995 ◽  
Vol 13 (10) ◽  
pp. 1090-1093 ◽  
Author(s):  
Ulrike Fiedler ◽  
Udo Conrad
1990 ◽  
Vol 212 ◽  
Author(s):  
D. E. Grandstaff ◽  
V. J. Grassi ◽  
A. C. Lee ◽  
G. C. Ulmer

ABSTRACTSystematic differences in pH, cation/proton ion activity ratios, and redox have been observed between solutions produced in rock-water hydrothermal experiments with tuff, granite, and basalt. Stable pH values in tuff-water experiments may be as much as 1.5 pH units more acidic than basalt-water experiments at the same temperature and ionic strength. Redox (log fO2) values in 300°C tuff experiments are 4–7 orders of magnitude more oxidizing than basalt experiments and ca. 4 log units more oxidizing than the magnetite-hematite buffer. Such fluid differences could significantly affect the performance of a high-level nuclear waste repository and should be considered in repository design and siting.


Catalysts ◽  
2019 ◽  
Vol 9 (4) ◽  
pp. 326 ◽  
Author(s):  
Olga Senko ◽  
Marina Gladchenko ◽  
Olga Maslova ◽  
Elena Efremenko

The aim of this paper is to demonstrate the possibilities of anaerobic sludge cells immobilized into poly(vinyl alcohol) cryogel for the methanogenic conversion of various lignocellulosic waste and other media containing antibiotics (ampicillin, kanamycin, benzylpenicillin) or pesticides (chlorpyrifos or methiocarb and its derivatives). It was established that the immobilized cells of the anaerobic consortium can be stored frozen for at least three years while preserving a high level of metabolic activity. The cells after the long-term storage in an immobilized and frozen state were applied for the methanogenesis of a wide number of wastes, and an increase in both methane yield and methane portion in the produced biogas as compared to the conventionally used suspended anaerobic sludge cells, was ensured. It was shown that the “additional” introduction of bacterial Clostridium acetobutylicum, Pseudomonas sp., Enterococcus faecalis cells (also immobilized using same support) improves characteristics of methanogenesis catalyzed by immobilized anaerobic sludge.


Author(s):  
Kenneth R. Trethewey

It is well known that some metals suffer damage caused by the evolution of hydrogen in certain conditions in nuclear applications. Of particular current interest is the use of alloys for use in containers for the long-term storage of high level nuclear waste. Calculations for the rates of corrosion of metals where hydrogen evolution is possible rely upon measurements of the reaction kinetics, but it is difficult to obtain reliable and accurate values for the kinetic constants. Standard electrochemical tests can be used, but the analysis of the results is complex because of the need to deconvolute the curves. This paper presents a computer model for the analysis of the data that is checked by its use on experimental data from a number of nuclear materials.


PLoS ONE ◽  
2022 ◽  
Vol 17 (1) ◽  
pp. e0262275
Author(s):  
Stephan Hilpmann ◽  
Miriam Bader ◽  
Robin Steudtner ◽  
Katharina Müller ◽  
Thorsten Stumpf ◽  
...  

The safe disposal of high-level radioactive waste in a deep geological repository is a huge social and technical challenge. So far, one of the less considered factors needed for a long-term risk assessment, is the impact of microorganisms occurring in the different host rocks. Even under the harsh conditions of salt formations different bacterial and archaeal species were found, e. g. Halobacterium sp. GP5 1–1, which has been isolated from a German rock salt sample. The interactions of this archaeon with uranium(VI), one of the radionuclides of major concern for the long-term storage of high-level radioactive waste, were investigated. Different spectroscopic techniques, as well as microscopy, were used to examine the occurring mechanisms on a molecular level leading to a more profound process understanding. Batch experiments with different uranium(VI) concentrations showed that the interaction is not only a simple, but a more complex combination of different processes. With the help of in situ attenuated total reflection Fourier-transform infrared spectroscopy the association of uranium(VI) onto carboxylate groups was verified. In addition, time-resolved laser-induced luminescence spectroscopy revealed the formation of phosphate and carboxylate species within the cell pellets as a function of the uranium(VI) concentration and incubation time. The association behavior differs from another very closely related halophilic archaeon, especially with regard to uranium(VI) concentrations. This clearly demonstrates the importance of studying the interactions of different, at first sight very similar, microorganisms with uranium(VI). This work provides new insights into the microbe-uranium(VI) interactions at highly saline conditions relevant to the long-term storage of radioactive waste in rock salt.


2006 ◽  
Vol 932 ◽  
Author(s):  
Damien Féron ◽  
Digby D. Macdonald

ABSTRACTThe corrosion resistance of container materials in underground repositories is an important issue for the safe disposal of High Level Nuclear Waste (HLNW). The reliable prediction of container degradation rate and engineering barrier integrity over extended periods, up to several thousands years or even several hundreds of thousands of years, represents one of the greatest scientific and technical challenges. The first and the second International Workshops on Prediction of Long Term Corrosion Behaviour in Nuclear Waste Systems, which were held in 2001 (Cadarache) and 2004 (Nice), sought to compare the scientific and experimental approaches that are being developed in various organisations worldwide for predicting long term corrosion phenomena, including corrosion strategies for interim storage and geological disposal. The lessons learned during these Workshops, include the necessity of developing two approaches based on semi-empiricism and determinism in a complementary manner for effective prediction. The use of archaeological artefacts to demonstrate the feasibility of long term storage and to provide a database for testing and validating modelling work was also emphasized.


1990 ◽  
Vol 212 ◽  
Author(s):  
Charles G. Interrante ◽  
Carla A. Messina ◽  
Anna C. Fraker

ABSTRACTThe work reported here is part of a program conducted by the Nuclear Regulatory Commission on the efficacy of proposed plans for radionuclide containment for long-term storage of high-level nuclear waste (HLW). An important element of that program is the review and evaluation of available literature on components of a waste package. A review process and a database have been developed and tailored to provide information quickly to an individual who has a question about a particular material or component of a waste package. The database is uniquely suited to serve as a guide to indicate special areas where data and information needs exist on questions related to radionuclide containment. Additions to the database are made as information becomes available, and this source is as current as the published literature. A description of the review process and the database is given.


1990 ◽  
Vol 3 (2) ◽  
pp. 143-166 ◽  
Author(s):  
Leigh Hancher

The article deals with the advantages and disadvantages of an international solution for the safe, permanent disposal or long-term storage of high level radioactive waste from a legal perspective. Firstly, some early attempts to create an International Waste Repository (IWR) and their subsequent fate are examined. Next to this, pros and cons of an IWR in the context of recent national and international developments in the management of, and trade in radioactive waste, are considered. Main related question is, whether an international solution to waste disposal is a useful option. Finally, the legal and institutional problems which must be considered if states decide to create an international facility for waste disposal are described. Special attention is given to a model provided for in Chapter V of the Euratom Treaty of 1957.


Author(s):  
Zenghu Han ◽  
Ralph Fabian ◽  
Ron Pope ◽  
Yung Liu ◽  
James Shuler

The U.S. Department of Energy (DOE) Packaging Certification Program (PCP), Office of Packaging and Transportation, Office of Environmental Management, has sponsored a suite of training courses that are conducted annually by Argonne National Laboratory (Argonne) in support of safety and security of nuclear and other radioactive material packages. One of these courses conducted by Argonne since 2000 is the Application of the ASME Code to Radioactive Material Transportation Packaging, which was expanded significantly in 2014 to include dry storage casks, resulting in a change in course title to the Application of the ASME Code to Radioactive Material Packaging/Cask. The purpose of the course is to provide guidance for the application of the American Society of Mechanical Engineers (ASME) Boiler and Pressure Vessel (BPV) Code (“ASME Code”) to transportation packaging and storage cask of radioactive materials, including used (or spent) nuclear fuel and high-level waste, and to facilitate the design, fabrication, examination, and testing of packagings and casks. Both regulatory requirements in 10 CFR Parts 71 and 72 and the ASME Code requirements for transportation and storage containments are addressed, with emphasis on the Code Section III, Division 3, “Containments for Transportation and Storage of Spent Nuclear Fuel and High Level Radioactive Material and Waste.” Among the specific topics covered are the application of the ASME Code requirements to structural materials, containments, loading and design; the design of containment internal support structures and buckling analysis; fabrication, welding, examination, and test requirements; quality assurance; physical testing, structural and thermal modeling and analysis considerations; and containment, shielding, and criticality analysis considerations. Special topics covered include non-Code materials, hydrogen gas generation, and aging management for extended long-term storage of used fuel and subsequent transportation. The expanded training course was offered in June 2014 at Argonne with 27 participants representing mainly industry and government agencies. On the basis of the feedback and course evaluation by the participants, the course may be expanded from 3 to 4.5 days in the future to allow more time for in-class discussion and exercises, as well as to include additional topics related to aging management for extended long-term storage of used fuel and its post-storage transportation. The course provides insight into the DOE and the U.S. Nuclear Regulatory Commission (NRC) transportation and storage cask certification processes. The target audience is DOE, DOE contractors, other agency personnel, and commercial transportation packaging and storage cask engineering employees. Those responsible for designing, fabricating, testing, or packaging and casks, as well as preparing or reviewing the associated Safety Analysis Reports, will also benefit from the course.


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