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Relevant bibliographies by topics / Radioactive wastes Transmutation

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Academic literature on the topic 'Radioactive wastes Transmutation'

Author: Grafiati

Published: 4 June 2021

Last updated: 15 February 2022

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Journal articles on the topic "Radioactive wastes Transmutation"

1

Salvatores, Massimo, and Claude Prunier. "Transmutation and nuclear radioactive wastes management: a perspective." Endeavour 17, no. 3 (1993): 116–20. http://dx.doi.org/10.1016/0160-9327(93)90100-h.

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Blagovolin, P. P., V. D. Kozaritskii, G. V. Kiselev, N. V. Lazarev, and I. V. Chuvilo. "Transmutation of long-lived radioactive wastes from nuclear power." Soviet Atomic Energy 70, no. 6 (1991): 469–75. http://dx.doi.org/10.1007/bf01123771.

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Ahn, Joonhong, Myeongguk Cheon, and Ehud Greenspan. "Effects of Accelerator-Driven Transmutation System on Radiotoxicity of High-Level Radioactive Wastes." Nuclear Technology 158, no. 3 (2007): 408–30. http://dx.doi.org/10.13182/nt07-a3851.

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Nuttall, W. J., D. G. Ireland, J. S. Al-Khalili, and W. Gelletly. "Potential for British research into the transmutation of radioactive wastes and problematic nuclear materials." International Journal of Critical Infrastructures 1, no. 4 (2005): 380. http://dx.doi.org/10.1504/ijcis.2005.006682.

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Akhter, Md Zishan, and M. Ashique Hassan. "Low Energy Nuclear Reaction (LENR) – Sustainable and Green Energy: A Review." Applied Mechanics and Materials 819 (January 2016): 507–11. http://dx.doi.org/10.4028/www.scientific.net/amm.819.507.

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In this paper a review on recent development in Low Energy Nuclear Reaction (LENR) is presented along with scope and challenges. As the name suggests Low Energy Nuclear Reaction (LENR) is a phenomenon of nuclear reaction occurring in metal hydrides at ambient temperature. The products are generally Helium & significant amount of useful heat energy. During the process Transmutation of metal (host) occurs; occasionally producing some charged particles and neutrons. The LENR are successfully carried out with various elements namely; nickel, gold, palladium, platinum, titanium, certain superconducting ceramics, etc. LENR poses itself as a source of pollution free and inexhaustible energy source. It produces tremendous amount of heat energy during the reaction which surpasses all the available energy sources by a factor of hundredths to millions. Besides this it is also useful in transmutation of nuclear wastes. To initiate LENR there are various views floating around in scientific community. The purpose is to bring together two nuclei at low energy to fuse together as a single nucleus. A large amount of force is required which is generally obtained through plasma arc or accelerated high energy ions. But in case of LENR all the nuclear reaction occur at low energy thus saving excessive amount of energy required for activation. One of the most studied LENR involves palladium. The palladium is used at a loading between 0.9 and 0.94 to produce optimum results. It is a source of Energy which is more eco-friendly and productive than all the available energy sources known to us. Statistically 1% of the total Ni production can power the World that too at one-fourth the cost of burning fossils. Models are being developed with Carbon replacing Ni, thus it will convert carbon to nitrogen. LENR is also being developed for using nuclear wastes as fuel, transmuting them into non-radioactive elements. This will tag LENR as much greener and cleaner source. LENR is being also developed to be used as an alternative and richer energy source to radioactive fuels (like Pu-238), currently being used to power space probes. Thus it helps reduce the generation of hazardous nuclear wastes.

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Moll, S., and L. Thomé. "Radiation Effects in Oxides Foreseen for the Immobilization and Transmutation of Radioactive Wastes: Case Study of Zirconia." Microscopy and Microanalysis 15, S2 (2009): 1344–45. http://dx.doi.org/10.1017/s143192760909391x.

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Anikeev, A. V., R. Dagan, and U. Fischer. "Numerical Model of the Fusion-Fission Hybrid System Based on Gas Dynamic Trap for Transmutation of Radioactive Wastes." Fusion Science and Technology 59, no. 1T (2011): 162–65. http://dx.doi.org/10.13182/fst11-1t5.

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Thomé, L., S. Moll, A. Debelle, F. Garrido, G. Sattonnay, and J. Jagielski. "Radiation Effects in Nuclear Ceramics." Advances in Materials Science and Engineering 2012 (2012): 1–13. http://dx.doi.org/10.1155/2012/905474.

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Due to outstanding physicochemical properties, ceramics are key engineering materials in many industrial domains. The evaluation of the damage created in ceramics employed in radiative media is a challenging problem for electronic, space, and nuclear industries. In this latter field, ceramics can be used as immobilization forms for radioactive wastes, inert fuel matrices for actinide transmutation, cladding materials for gas-cooled fission reactors, and structural components for fusion reactors. Information on the radiation stability of nuclear materials may be obtained by simulating the different types of interactions involved during the slowing down of energetic particles with ion beams delivered by various types of accelerators. This paper presents a review of the radiation effects occurring in nuclear ceramics, with an emphasis on recent results concerning the damage accumulation processes. Energetic ions in the KeV-GeV range are used to explore the nuclear collision (at low energy) and electronic excitation (at high energy) regimes. The recovery by electronic excitation of the damage created by ballistic collisions (SHIBIEC process) is also addressed.

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Fujita, Reiko. "Toward the fusion of science and engineering through innovative approaches for reduction and resource recycling of high- level radioactive wastes with nuclear transmutation." Journal of the Atomic Energy Society of Japan 58, no. 2 (2016): 93–95. http://dx.doi.org/10.3327/jaesjb.58.2_93.

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Maltseva, T., А. Shyshuta, and S. Lukashyn. "Modern Methods of Radiochemical Reprocessing of Spent Nuclear Fuel." Nuclear and Radiation Safety, no. 1(81) (March 12, 2019): 52–57. http://dx.doi.org/10.32918/nrs.2019.1(81).09.

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The paper is devoted to the history of development and the current state of technological and scientific advances in radiochemical reprocessing of spent nuclear fuel from water-cooled power reactors. Regarding spent nuclear fuel (SNF) of NPP power reactors, long-term energy security involves adopting a version of its radiochemical treatment, conditioning and recirculation. Recycling SNF is required for the implementation of a closed fuel cycle and the re-use of regeneration products as energy reactor fuels. The basis of modern technological schemes for the reprocessing of the spent nuclear fuel is the “Purex” process, developed since the 60s in the USA. The classic approach to the use of U and Pu nuclides contained in spent nuclear fuel is to separate them from fission products, re-enrich regenerated uranium and use plutonium for the production of mixed-oxide (MOX) fuel with depleted uranium. The modern reprocessing plants are able to deal with fuel with further increase of its main characteristics without significant changes in the initial project. In order to close the fuel cycle, it is needed to add the following technological steps: (1) removal of high-level and long-lived components and minor actinides; (2) return of actinides to the technological cycle; (3) safe disposal of unused components. Each of these areas is under investigation now. Several new promising multi-cycle hydrometallurgical processes based on the joint extraction of trivalent lanthanides and minor actinides with their subsequent separation have been developed. A number of promising materials is suggested to be potential matrices for the immobilization of high-level components of radioactive wastes. To improve the compatibility of fuel processing with the environment, non-aqueous technologies are being developed, for instance, pyro-chemical methods for the reprocessing of various types of highly active fuels based on metals, oxides, carbides, or nitrides. An important scientific and technological task under investigation is transmutation of actinides. The results of international large-scale experiments on the partitioning and transmutation of fuel with various minor actinides and long-lived fission products confirm the real possibility and expediency of closing the nuclear fuel cycle.

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Dissertations / Theses on the topic "Radioactive wastes Transmutation"

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Hoffman, Edward Albert. "Neutron transmutation of nuclear waste." Diss., Georgia Institute of Technology, 2002. http://hdl.handle.net/1853/16700.

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Mauer, Andrew N. "A superconducting fusion transmutation of waste reactor." Thesis, Georgia Institute of Technology, 2002. http://hdl.handle.net/1853/15970.

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Maddox, James Warren. "Fuel Cycle Optimization of a Helium-Cooled, Sub-Critical, Fast Transmutation of Waste Reactor with a Fusion Neutron Source." Thesis, Available online, Georgia Institute of Technology, 2006, 2006. http://etd.gatech.edu/theses/available/etd-03222006-174421/.

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O'Kelly, David Sean 1961. "Operation and reactivity measurements of an accelerator driven subcritical TRIGA reactor." Thesis, 2008. http://hdl.handle.net/2152/3973.

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Experiments were performed at the Nuclear Engineering Teaching Laboratory (NETL) in 2005 and 2006 in which a 20 MeV linear electron accelerator operating as a photoneutron source was coupled to the TRIGA (Training, Research, Isotope production, General Atomics) Mark II research reactor at the University of Texas at Austin (UT) to simulate the operation and characteristics of a full-scale accelerator driven subcritical system (ADSS). The experimental program provided a relatively low-cost substitute for the higher power and complexity of internationally proposed systems utilizing proton accelerators and spallation neutron sources for an advanced ADSS that may be used for the burning of high-level radioactive waste. Various instrumentation methods that permitted ADSS neutron flux monitoring in high gamma radiation fields were successfully explored and the data was used to evaluate the Stochastic Pulsed Feynman method for reactivity monitoring.<br>text

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Books on the topic "Radioactive wastes Transmutation"

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Lammer, M. Fission product yield data for the transmutation of minor actinide nuclear waste. International Atomic Energy Agency, 2008.

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2

Damen, Patricia Maria Gerardina. Helium and fission gas behaviour in magnesium aluminate spinel and zirconia for actinide transmutation. DUP Science, 2003.

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3

Implications of partitioning and transmutation in radioactive waste management. International Atomic Energy Agency, 2004.

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4

National Research Council (U.S.). Committee on Separations Technology and Transmutation Systems., ed. Nuclear wastes: Technologies for separations and transmutation. National Academy Press, 1996.

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(US), National Research Council. Nuclear Wastes: Technologies for Separations and Transmutation. National Academies Press, 1996.

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6

Agency, International Atomic Energy, ed. Disposal options for disused radioactive sources. International Atomic Energy Agency, 2005.

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7

Kh, Khankhasaev M., Kurmanov Zh B, Plendl Hans S, and International Workshop on Nuclear Methods for Transmutation of Nuclear Waste: Problems, Perspectives, Cooperative Research (1996 : Dubna, Russia), eds. Proceedings of the international workshop, nuclear methods for transmutation of nuclear waste: Problems, perspectives, cooperative research. World Scientific, 1997.

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Nuclear Methods for Transmutation of Nuclear Waste - Problems, Perspectives, Cooperative Research: Proceedings of the International Workshop. World Scientific Pub Co Inc, 1997.

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Implications of Partitioning And Transmutation in Radioactive Waste Management: Technical Reports (Technical Reports Series (International Atomic Energy Agency)). Intl Atomic Energy Agency, 2005.

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Book chapters on the topic "Radioactive wastes Transmutation"

1

Fujikawa, Yoko, Hiroaki Ozaki, Hiroshi Tsuno, et al. "Volume Reduction of Municipal Solid Wastes Contaminated with Radioactive Cesium by Ferrocyanide Coprecipitation Technique." In Nuclear Back-end and Transmutation Technology for Waste Disposal. Springer Japan, 2014. http://dx.doi.org/10.1007/978-4-431-55111-9_29.

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Yoshida, Akemi. "Considering the Geological Disposal Program of High-Level Radioactive Waste Through Classroom Debate." In Nuclear Back-end and Transmutation Technology for Waste Disposal. Springer Japan, 2014. http://dx.doi.org/10.1007/978-4-431-55111-9_25.

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3

Yamawaki, Michio, Kenji Konashi, Koji Fujimura, and Toshikazu Take. "Substantial Reduction of High Level Radioactive Waste by Effective Transmutation of Minor Actinides in Fast Reactors Using Innovative Targets." In Radioactive Waste. InTech, 2012. http://dx.doi.org/10.5772/33441.

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4

Warin, D. M. "Developments in the partitioning and transmutation of radioactive waste." In Advanced Separation Techniques for Nuclear Fuel Reprocessing and Radioactive Waste Treatment. Elsevier, 2011. http://dx.doi.org/10.1533/9780857092274.3.363.

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Salvatores, M. "Partitioning and transmutation of spent nuclear fuel and radioactive waste." In Nuclear Fuel Cycle Science and Engineering. Elsevier, 2012. http://dx.doi.org/10.1533/9780857096388.4.501.

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Hill, C. "Development of highly selective compounds for solvent extraction processes: partitioning and transmutation of long-lived radionuclides from spent nuclear fuels." In Advanced Separation Techniques for Nuclear Fuel Reprocessing and Radioactive Waste Treatment. Elsevier, 2011. http://dx.doi.org/10.1533/9780857092274.3.311.

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Conference papers on the topic "Radioactive wastes Transmutation"

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Oigawa, Hiroyuki. "Transmutation of Long-Lived Nuclear Wastes." In Proceedings of the Conference on Advances in Radioactive Isotope Science (ARIS2014). Journal of the Physical Society of Japan, 2015. http://dx.doi.org/10.7566/jpscp.6.010004.

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Anikeev, Andrey V. "Optimisation of the neutron source based on gas dynamic trap for transmutation of radioactive wastes." In FUSION FOR NEUTRONS AND SUBCRITICAL NUCLEAR FISSION: Proceedings of the International Conference. AIP, 2012. http://dx.doi.org/10.1063/1.4706863.

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Fujita, Reiko, Masatoshi Kawashima, Masaki Ozawa, and Teiichiro Matsuzaki. "Reduction and Resource Recycling of High-level Radioactive Wastes through Nuclear Transmutation —Overview and Current Progress—." In Proceedings of 13th International Conference on Nucleus-Nucleus Collisions. Journal of the Physical Society of Japan, 2020. http://dx.doi.org/10.7566/jpscp.32.010098.

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4

Kim, Sung-yeop, and Kun Jai Lee. "Scenario Development for Safety Assessment of Waste Repository for Feasibility Study on Transmutation of Spent Nuclear Fuel Into LILW Using PEACER." In ASME 2010 13th International Conference on Environmental Remediation and Radioactive Waste Management. ASMEDC, 2010. http://dx.doi.org/10.1115/icem2010-40209.

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PEACER (Proliferation-resistant, Environmental-friendly, Accident-tolerant, Continuable-energy and Economical Reactor) is a conceptual liquid metal fast reactor using Pb-Bi as a coolant and feasibility study on transmutation of spent nuclear fuel into LILW (Low and Intermediate Level Waste) using PEACER is in progress. Safety assessment of repository is essential for this feasibility study with assumption that we dispose the wastes from PWRs and PEACERs with established decontamination factors. Scenario development is one of important step for carrying out reliable and comprehensive safety assessment. This study adopted scenario development methodology from H12 report (JNC, 2000) and classified assessment scenarios into base scenario, perturbation scenarios and isolation failure scenarios. Scenarios are established by classifying, screening out and selecting FEPs with concepts and conditions of disposal for feasibility study.

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Gerasimov, Aleksander S., Boris R. Bergelson, and Tamara S. Zaritskaya. "Two Periods of Long-Term Storage of Thorium Spent Fuel." In ASME 2001 8th International Conference on Radioactive Waste Management and Environmental Remediation. American Society of Mechanical Engineers, 2001. http://dx.doi.org/10.1115/icem2001-1219.

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Abstract Radiotoxicity and decay heat power of actinides from spent thorium-uranium nuclear fuel of VVER-1000 type reactor during 100 000 year storage are discussed. Actinide accumulation in thorium fuel cycle is much less than in uranium fuel cycle. The radiotoxicity of actinides of thorium-uranium fuel by air is 5.5 times less and radiotoxicity by water is 3.5 times less than radiotoxicity of actinides of uranium fuel. Extraction of most important nuclides for transmutation permits to reduce radiologic danger of wastes remaining in storage.

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Golovkina, Anna, Sorin Olaru, and Dmitri Ovsyannikov. "A Robust Optimization Model for the Radioactive Waste Transmutation in ADS." In 2019 6th International Conference on Control, Decision and Information Technologies (CoDIT). IEEE, 2019. http://dx.doi.org/10.1109/codit.2019.8820561.

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Bacha, F., J. Maillard, and J. Silva. "Simulation of radioactive waste transmutation on the T. Node parallel computer." In The international conference on accelerator-driven transmutation technologies and applications. AIP, 1995. http://dx.doi.org/10.1063/1.49163.

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Csom, Gyula, Sandor Feher, and Mate Szieberth. "A Novel Molten Salt Reactor Concept to Implement the Multi-Step Time-Scheduled Transmutation Strategy." In 10th International Conference on Nuclear Engineering. ASMEDC, 2002. http://dx.doi.org/10.1115/icone10-22688.

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Nowadays the molten salt reactor (MSR) concept seems to revive as one of the most promising systems for the realization of transmutation. In the molten salt reactors and subcritical systems the fuel and material to be transmuted circulate dissolved in some molten salt. The main advantage of this reactor type is the possibility of the continuous feed and reprocessing of the fuel. In the present paper a novel molten salt reactor concept is introduced and its transmutational capabilities are studied. The goal is the development of a transmutational technique along with a device implementing it, which yield higher transmutational efficiencies than that of the known procedures and thus results in radioactive waste whose load on the environment is reduced both in magnitude and time length. The procedure is the multi-step time-scheduled transmutation, in which transformation is done in several consecutive steps of different neutron flux and spectrum. In the new MSR concept, named “multi-region” MSR (MRMSR), the primary circuit is made up of a few separate loops, in which salt-fuel mixtures of different compositions are circulated. The loop sections constituting the core region are only neutronically and thermally coupled. This new concept makes possible the utilization of the spatial dependence of spectrum as well as the advantageous features of liquid fuel such as the possibility of continuous chemical processing etc. In order to compare a “conventional” MSR and a proposed MRMSR in terms of efficiency, preliminary calculational results are shown. Further calculations in order to find the optimal implementation of this new concept and to emphasize its other advantageous features are going on.

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Tikhonov, V. I., P. N. Moskalev, and V. K. Kapustin. "The Carbon Matrices Made of Pyrolised Phtalocyanines as a Base for Encapsulation of the Long-Lived Nuclides of Iodine, Technetium and Minor Actinides." In The 11th International Conference on Environmental Remediation and Radioactive Waste Management. ASMEDC, 2007. http://dx.doi.org/10.1115/icem2007-7084.

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The creation and careful investigation of suitable materials and forms for transmutation of the long-lived radioactive waste (RW) is mainly in the starting stage. A new carbon material formed as a result of pyrolisis of bisphtalocyanine, Pc2Me, gives a chance to solve this goal successfully. The pyrolysis takes place under an argon (Ar) atmosphere at temperature of 700 – 800°C. The release of atoms encapsulated inside this carbon matrix occurs only at temperatures above 1200°C, and a correlation between the efficiency of the atoms’ release and their atomic radius has been revealed. It is caused with creation of closed microcavities in the carbon skeleton during pyrolysis of MeC2. Due to inert features and high thermostability of carbon, an inculcation of the long-lived radionuclides in these microcavities by means of their phtalocyanines pyrolysis gives unique opportunities for both their transmutation and storage. The first results on encapsulation within matrixes of radionuclides of europium (Eu), technetium (Tc), iodine (I) and “minor actinides” are presented. The efficiency of encapsulation is close to 100% for all studied elements excluding iodine, for the last one, it is near 85–90%. The results on thermochemical stability, leaching and other tests of these matrixes are presented.

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Rechard, Rob P., Joon Lee, Mark Sutton, Harris R. Greenberg, Bruce A. Robinson, and W. Mark Nutt. "Impact of Advanced Fuel Cycles on Uncertainty Associated With Geologic Repositories." In ASME 2013 15th International Conference on Environmental Remediation and Radioactive Waste Management. American Society of Mechanical Engineers, 2013. http://dx.doi.org/10.1115/icem2013-96211.

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This paper provides a qualitative evaluation of the impact of advanced fuel cycles, particularly partition and transmutation of actinides, on the uncertainty associated with geologic disposal. Based on the discussion, advanced fuel cycles, will not materially alter (1) the repository performance, (2) the spread in dose results around the mean, (3) the modeling effort to include significant features, events, and processes in the performance assessment, or (4) the characterization of uncertainty associated with a geologic disposal system in the regulatory environment of the United States.

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Reports on the topic "Radioactive wastes Transmutation"

1

Forsberg, C. W., A. G. Croff, and D. C. Kocher. Historical perspective, economic analysis, and regulatory analysis of the impacts of waste partitioning-transmutation on the disposal of radioactive wastes. Office of Scientific and Technical Information (OSTI), 1990. http://dx.doi.org/10.2172/6402235.

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Toor, A., and R. Buck. Transmutation of radioactive nuclear waste. Office of Scientific and Technical Information (OSTI), 2000. http://dx.doi.org/10.2172/15005725.

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