A5021876597- Radioactive element chemistry and processing
- Chemical Synthesis and Characterization
- Graphite, nuclear technology, radiation studies
- Nuclear and radioactivity studies
- Extraction and Separation Processes
- Nuclear Materials and Properties
- Radioactive contamination and transfer
- Nuclear materials and radiation effects
- Nuclear reactor physics and engineering
- Molten salt chemistry and electrochemical processes
- Analytical chemistry methods development
- Radioactivity and Radon Measurements
- Thermal and Kinetic Analysis
- Risk and Safety Analysis
- Glass properties and applications
- Metal Extraction and Bioleaching
- Spacecraft and Cryogenic Technologies
- Catalytic Processes in Materials Science
- Nuclear Physics and Applications
- Material Properties and Applications
- Groundwater flow and contamination studies
- Recycling and Waste Management Techniques
- Arsenic contamination and mitigation
- Recycling and utilization of industrial and municipal waste in materials production
- Advanced Materials Characterization Techniques
Leibniz University Hannover
2016-2023
Westinghouse Electric (United States)
1988-1995
Waste Management (United States)
1995
MACOM (United States)
1993
Argonne National Laboratory
1991
UNSW Sydney
1990
Rockwell Automation (United States)
1977-1987
ExxonMobil (United States)
1982
Linde (United States)
1982
Battelle
1966-1972
Abstract The TRUEX (TRansUranium Extraction) process is a new generic actinide extraction/recovery for the removal of all actinides from acidic nitrate and chloride nuclear waste solutions. A brief review relevant chemistry summary current status development deployment flowsheets to treat specific solutions at several U.S. DOE sites presented.
Abstract A principal purpose of this paper is to call out what perceived be a timely need for increased research develop improved and new solvent extraction technology recovery 137Cs 90Sr from strong (≥ 0.5M HNO3) acid media, which can quickly scaled up routine plant-scale operation with highly radioactive waste solutions when needed. The present forseeable future (2020) U.S. inventory 90sr listed; much expected available only in strongly acidic nuclear solutions. Comparison...
ADVERTISEMENT RETURN TO ISSUEPREVArticleNitric Acid Dissolution of Uranium-Molybdenum Alloy Reactor FuelsW. W. Schulz, R. E. Burns, and M. DukeCite this: Ind. Eng. Chem. Process Des. Dev. 1962, 1, 2, 156–160Publication Date (Print):April 1962Publication History Published online1 May 2002Published inissue 1 April 1962https://pubs.acs.org/doi/10.1021/i260002a017https://doi.org/10.1021/i260002a017research-articleACS PublicationsRequest reuse permissionsArticle Views205Altmetric-Citations10LEARN...
Microscopic fuel fragments, so-called "hot particles", were released during the 1986 accident at Chornobyl nuclear powerplant and continue to contaminate exclusion zone in northern Ukraine. Isotopic analysis can provide vital information about sample origin, history contamination of environment, though it has been underutilized due destructive nature most mass spectrometric techniques, inability remove isobaric interference. Recent developments have diversified range elements that be...
ADVERTISEMENT RETURN TO ISSUEPREVArticleNEXTSolvent Extraction Recovery and Purification of Strontium-90W. W. Schulz, J. E. Mendel, G. L. RichardsonCite this: Ind. Eng. Chem. Process Des. Dev. 1963, 2, 134–140Publication Date (Print):April 1, 1963Publication History Published online1 May 2002Published inissue 1 April 1963https://pubs.acs.org/doi/10.1021/i260006a009https://doi.org/10.1021/i260006a009research-articleACS PublicationsRequest reuse permissionsArticle...
Abstract American and Russian workers have evidenced great interest in the last decadejn potential application of certain neutral'and acidic bifunctional organophosphorus compounds solvent extraction processes. Triggering this is ability some carbamoylmethylenephosphorus (CMP) carbamoylmethylenephosphine oxide (CMPO) to extract trivalent actinides lanthanides from strong HNC>3 (>1 M) solutions, a property which distinguishes them monofunctional reagents. Investigators at several U.S....
ADVERTISEMENT RETURN TO ISSUEPREVArticleNEXTTrilaurylamine Extraction of Neptunium and Plutonium from Purex Process WasteW. W. SchulzCite this: Ind. Eng. Chem. Des. Dev. 1967, 6, 1, 115–121Publication Date (Print):January 1967Publication History Published online1 May 2002Published inissue 1 January 1967https://pubs.acs.org/doi/10.1021/i260021a020https://doi.org/10.1021/i260021a020research-articleACS PublicationsRequest reuse permissionsArticle Views146Altmetric-Citations7LEARN ABOUT THESE...