Processes for Removal and Immobilization of 14C, 129I, and 85Kr

Strachan, Denis M.; Bryan, Samuel A.; Henager, Charles H.; Levitskaia, Tatiana G.; Matyáš, Josef; Thallapally, Praveen K.; Scheele, R.D.; Weber, William J.; Zheng, Feng

doi:10.2172/1009773

Cited by 4 publications

(3 citation statements)

References 93 publications

(106 reference statements)

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“…The sol-gel process used to create aerogels allows for the alteration of chemical makeup, modification of the organosilane and deposition of chemical layers. This allows the micropores in aerogels to be highly customizable and effective for the removal of radionuclides [76]. Zeolites attract a great interest in the field of noble gas sorption due to their physical properties (high specific capacity, structural stability and small pore size).…”

Section: Sorbents For Capture Of Radioactive Volatile Iodinementioning

confidence: 99%

“…The loading of silver nanoparticles onto zeolites or silicotitanate has been reported to result in an increased affinity over the non-modified parent materials for noble gases. This Ag + metal center interacts with the noble gas in what is described as a weak Lewis acid (metal)/base (noble gas) affinity [76]. Kuznicki et al reported the strong interaction on Ag-ETS-10 to a specific interaction of xenon with silver nanoparticles observed at the external surface of zeolite.…”

Section: Sorbents For Capture Of Radioactive Volatile Iodinementioning

confidence: 99%

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Capture of harmful radioactive contaminants from off-gas stream using porous solid sorbents for clean environment – A review

Nandanwar

Coldsnow

Utgikar

et al. 2016

Chemical Engineering Journal

275

150

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Nuclear energy production is growing rapidly worldwide to satisfy increasing energy demands. Reprocessing of used nuclear fuel (UNF) is expected to play an important role for sustainable development of nuclear energy by increasing the energy extracted from the fuel and reducing the generation of the high level waste (HLW). However, during the reprocessing of Used Nuclear Fuel (UNF) gaseous radioactive nuclides including iodine, krypton, xenon, carbon, and tritium are released into the atmosphere through off-gas streams.The volatile iodine ( 129 I), and krypton ( 85 Kr) gases have long lived-isotopes; which have adverse effects on the environment as well as human health. Consequently, the capture of these two target radionuclides (species) is essential for the enhanced growth of nuclear energy. In this review we discuss several techniques for capture of volatile contaminants iodine, krypton, and xenon, focusing upon adsorption using solid sorbents, which has shown promising results for more than 70 years. Commonly used and recently developed sorbents are summarized in this article along with a short review of the results. Metal-organicframeworks (MOFs), gaining favor in recent years as sorbents for the capture of off-gas contaminants are also discussed. Finally, some considerations of future trends and prospects for investigations of the capture of volatile radionuclides are presented.

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Section: Sorbents For Capture Of Radioactive Volatile Iodinementioning

confidence: 99%

Section: Sorbents For Capture Of Radioactive Volatile Iodinementioning

confidence: 99%

Capture of harmful radioactive contaminants from off-gas stream using porous solid sorbents for clean environment – A review

Nandanwar

Coldsnow

Utgikar

et al. 2016

Chemical Engineering Journal

275

150

View full text Add to dashboard Cite

show abstract

“…In the case of nuclear waste in a repository, significant heating is possible: self-heating from ȕ-decay of fission products can result in initial storage temperatures greater than 200qC for non-U.S. commercial HLW glass [Weber et al, 1998]; at desired high waste loadings, storage temperature of Cs/Sr waste forms could be up to 1000qC [Weber et al, 2009]. In our study, the measured sample temperature rise under ion beam irradiations at room temperature is ~10qC; while, the calculated temperature rise from electronbeam-heating is between 1050qC, depending on different theoretical models and target materials.…”

Section: Fcrdͳswfͳ12ͳ000073 139 Revision 1 February 2013mentioning

confidence: 99%

Separations and Waste Forms Research and Development FY 2013 Accomplishments Report

None¹

2013

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Cover Graphics: [background] This report briefly outlines campaign management and integration activities, but the intent of the report is to highlight the many technical accomplishments made during FY 2012. The campaign continued to maintain a balanced effort between scientific investigations to underpin advanced separations and waste forms technologies and engineering advancement to maintain relevance and focus on implementable technologies. There was an increased focus on development of new tools and methods to develop a better fundamental understanding of separation processes and waste form behavior and this effort is closely tied to modeling and simulation activities.The SWFC campaign management and integration activities included international coordination activities (France, China, Russia, Japan, and the International Atomic Energy Agency [IAEA] Advanced Aqueous TechnologiesWork performed within Advanced Aqueous Technologies was primarily the development of capabilities to support generic aqueous separation technologies (i.e., areas of development that will be needed and important for any aqueous technology). These included spectrophotometric monitoring of key process parameters (e.g., U, Pu, Np, nitrate, acid concentration) in near-real time. Additionally, the same techniques were applied to detecting and monitoring solvent degradation products and measuring metal concentrations in molten salt environments. A state-of-the-art micro-capillary sampling system was developed and designed for taking process samples, transporting them to an instrument and performing the analysis. A solvent degradation test loop, to allow hydrolysis and radiolysis (or both) of process solvents to be tested was used to test the Separations and Waste Forms Accomplishments Report vi FCRDͲSWFͲ12Ͳ000073 Revision 1, February 2013solvent degradation behavior of the TRUEX process. The test loop, which is one of only two in the world, gives the SWFC the ability to test the solvent degradation of any process solvent planned for future testing or implementation. Finally, additional testing of the Modified Direct Denitration process for conversion of uranium and actinide nitrates to oxides was performed. Electrochemical Separation TechnologiesWork performed under this area includes fission product and TRU drawdown from spent salt, process monitoring of metals in molten salt using volumetric and spectrophotometric techniques, , and salt-metal separations for U/TRU product. An additional project focused on limited recycle using molybdate melts was selected as part of an FY 2011 call for white papers and work was completed in FY 2012. These are areas that fall outside of the Joint Fuel Cycle Studies project and are focused on long term improvements for the electrochemical processing technology. Sigma Team for Minor Actinide SeparationsThis multi-lab, multidisciplinary Sigma Team is taking a number of approaches at trying to develop a simplified, economic and robust separation scheme for Am from Cm and lanthanides or Am and Cm from lanthanid...

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Radiation Induced Effects in CMCs for Advanced Nuclear Energy Systems

Nikoli

Matovi

2021

Encyclopedia of Materials: Composites

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Processes for Removal and Immobilization of 14C, 129I, and 85Kr

Cited by 4 publications

References 93 publications

Capture of harmful radioactive contaminants from off-gas stream using porous solid sorbents for clean environment – A review

Capture of harmful radioactive contaminants from off-gas stream using porous solid sorbents for clean environment – A review

Separations and Waste Forms Research and Development FY 2013 Accomplishments Report

Radiation Induced Effects in CMCs for Advanced Nuclear Energy Systems

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