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Artigos de revistas sobre o tema "Metallic nuclear waste"

Autor: Grafiati

Publicado: 19 de abril de 2025

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1

Stoulil, J., and D. Dobrev. "Microbial corrosion of metallic materials in a deep nuclear-waste repository." Koroze a ochrana materialu 60, no. 2 (2016): 59–67. http://dx.doi.org/10.1515/kom-2016-0010.

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AbstractThe study summarises current knowledge on microbial corrosion in a deep nuclear-waste repository. The first part evaluates the general impact of microbial activity on corrosion mechanisms. Especially, the impact of microbial metabolism on the environment and the impact of biofilms on the surface of structure materials were evaluated. The next part focuses on microbial corrosion in a deep nuclear-waste repository. The study aims to suggest the development of the repository environment and in that respect the viability of bacteria, depending on the probable conditions of the environment,

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Dietz, N. L., and D. D. Keiser. "TEM Analysis of Corrosion Products From a Radioactive Stainless Steel-based Alloy." Microscopy and Microanalysis 6, S2 (2000): 368–69. http://dx.doi.org/10.1017/s1431927600034334.

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Argonne National Laboratory has developed an electrometallurgical treatment process for metallic spent nuclear fuel from the Experimental Breeder Reactor-II. This process stabilizes metallic sodium and separates usable uranium from fission products and transuranic elements that are contained in the fuel. The fission products and other waste constituents are placed into two waste forms: a ceramic waste form that contains the transuranic elements and active fission products such as Cs, Sr, I and the rare earth elements, and a metal alloy waste form composed primarily of stainless steel (SS), fro

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Janney, D. E., and D. D. Keiser. "Actinides in metallic waste from electrometallurgical treatment of spent nuclear fuel." JOM 55, no. 9 (2003): 59–60. http://dx.doi.org/10.1007/s11837-003-0032-z.

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4

Holt, Erika, Maria Oksa, Matti Nieminen, et al. "Predisposal conditioning, treatment, and performance assessment of radioactive waste streams." EPJ Nuclear Sciences & Technologies 8 (2022): 40. http://dx.doi.org/10.1051/epjn/2022036.

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Before the final disposal of radioactive wastes, various processes can be implemented to optimise the waste form. This can include different chemical and physical treatments, such as thermal treatment for waste reduction, waste conditioning for homogenisation and waste immobilisation for stabilisation prior to packaging and interim storage. Ensuring the durability and safety of the waste matrices and packages through performance and condition assessment is important for waste owners, waste management organisations, regulators and wider stakeholder communities. Technical achievements and lesson

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Barton, Daniel N. T., Thomas Johnson, Anne Callow, et al. "A review of contamination of metallic surfaces within aqueous nuclear waste streams." Progress in Nuclear Energy 159 (May 2023): 104637. http://dx.doi.org/10.1016/j.pnucene.2023.104637.

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Moiseenko, V., and S. Chernitskiy. "Nuclear Fuel Cycle with Minimized Waste." Nuclear and Radiation Safety, no. 1(81) (March 12, 2019): 30–35. http://dx.doi.org/10.32918/nrs.2019.1(81).05.

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A uranium-based nuclear fuel and fuel cycle are proposed for energy production. The fuel composition is chosen so that during reactor operation the amount of each transuranic component remains unchanged since the production rate and nuclear reaction rate are balanced. In such a ‘balanced’ fuel only uranium-238 content has a tendency to decrease and, to be kept constant, must be sustained by continuous supply. The major fissionable component of the fuel is plutonium is chosen. This makes it possible to abandon the use of uranium-235, whose reserves are quickly exhausted. The spent nuclear fuel

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7

Janney, Dawn E. "Host phases for actinides in simulated metallic waste forms." Journal of Nuclear Materials 323, no. 1 (2003): 81–92. http://dx.doi.org/10.1016/j.jnucmat.2003.08.032.

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Rodríguez, Martín A. "Anticipated Degradation Modes of Metallic Engineered Barriers for High-Level Nuclear Waste Repositories." JOM 66, no. 3 (2014): 503–25. http://dx.doi.org/10.1007/s11837-014-0873-7.

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Janney, D. E. "Incorporation of Actinide Elements into Iron-Zirconium Intermetallic Phases in Metallic Waste Forms for High-Level Nuclear Waste." Microscopy and Microanalysis 8, S02 (2002): 1310–11. http://dx.doi.org/10.1017/s1431927602104983.

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Pavliuk, Alexander O., Evgeniy V. Bespala, Sergey G. Kotlyarevskiy, Ivan Yu Novoselov, and Veleriy N. Kotov. "Analysis of Heat Release Processes inside Storage Facilities Containing Irradiated Nuclear Graphite." Science and Technology of Nuclear Installations 2022 (January 30, 2022): 1–13. http://dx.doi.org/10.1155/2022/2957310.

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The article is dedicated to the safety assessment of mixed storage of irradiated graphite and other types of radioactive waste accumulated during the operation of uranium-graphite reactors. The analysis of heat release processes inside storages containing irradiated nuclear graphite, representing a potential hazard due to the possible heating and, accordingly, the release of long-lived radionuclides during oxidation was carried out. The following factors were considered as the main factors that can lead to an increase in the temperature inside the storage facility: corrosion of metallic radioa

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Pieraccini, Michel, and Sylvain Granger. "A nuclear owner/operator perspective on ways and means for joint programming on predisposal activities." EPJ Nuclear Sciences & Technologies 6 (2020): 20. http://dx.doi.org/10.1051/epjn/2019039.

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Nuclear decommissioning is a worldwide competitive market. It is also the main source of radioactive waste from the nuclear energy field. In order to reduce the waste volume it is necessary to sort the actual radioactive waste to be disposed of and to separate them from other materials that could be recycled. Since 2015, Electricité de France (EDF) has gathered the waste management and dismantling (WM&D) projects, the related competences and human resources in the WM&D field, in a dedicated directorate (DP2D) and a company group called Cyclife (including waste treatment facilities). Ta

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12

Galoisy, L., G. Calas, G. Morin, S. Pugnet, and C. Fillet. "Structure of Pd–Te precipitates in a simulated high-level nuclear waste glass." Journal of Materials Research 13, no. 5 (1998): 1124–27. http://dx.doi.org/10.1557/jmr.1998.0158.

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Structural and bonding characteristics of simplified (Pd, Te) precipitates have been determined in a simulated nuclear French glass using extended x-ray absorption fine structure (EXAFS) and x-ray diffraction. In this sample, these precipitates have a homogeneous composition, with about 10 wt.% Te. They retain a face-centered cubic structure as in pure Pd with a cell parameter which obeys Vegard's law. Pd K-edge EXAFS shows the presence of Te in the Pd coordination shell, with (Pd–Te) distances of 2.80 Å. These distances, higher by 0.05 Å than the (Pd–Pd) distances, may result in a lower packi

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13

Rébiscoul, Diane, Emilien Burger, Florence Bruguier, et al. "Glass-Iron-Clay interactions in a radioactive waste geological disposal: a multiscale approach." MRS Proceedings 1518 (2013): 185–90. http://dx.doi.org/10.1557/opl.2013.67.

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ABSTRACTIn France, nuclear glass canisters arising from spent fuel reprocessing are expected to be disposed in a deep geological repository using a multi-barrier concept (glass/canister/steel overpack and claystone). In this context, glass - iron or corrosion products interactions were investigated in a clayey environment to better understand the mechanisms and driving forces controlling the glass alteration. Integrated experiments involving glass - metallic iron or magnetite - clay stacks were run at laboratory scale in anoxic conditions for two years. The interfaces were characterized by a m

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14

Mednikov, I. V., V. V. Vasilyev, A. S. Busygin, and A. A. Sobko. "Provision of the radiation safety for the decomissioning of the heavy-water research nuclear reactor NRC «Kurchatov Institute» – ITEP." Radiatsionnaya Gygiena = Radiation Hygiene 13, no. 1 (2020): 74–83. http://dx.doi.org/10.21514/1998-426x-2020-13-1-74-83.

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The article provides a brief description of organizational and technical measures aimed at ensuring radiation safety during the decommissioning of the heavy-water research nuclear reactor of Institute for Theoretical and Experimental Physics after A.I. Alikhanov of National Research Centre «Kurchatov Institute». Information is provided on the history and features of the operation of the reactor, including parameters and characteristics that are significant for planning and conducting work. The peculiarities of legal regulation in the field of ensuring radiation safety are given; regulatory act

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15

Lemont, Florent, Patrice Charvin, Aldo Russello, and Karine Poizot. "An Innovative Hybrid Process Involving Plasma in a Cold Crucible Melter Devoted to the Futur Intermediate Level Waste Treatment: The SHIVA Technology." Advances in Science and Technology 73 (October 2010): 148–57. http://dx.doi.org/10.4028/www.scientific.net/ast.73.148.

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The cold crucible technology first developed for the treatment of the high level fission products can also be used for the direct treatment of intermediate level wastes. In this case, the wastes can be under the states of liquids or solids. The first experiments carried out for the direct treatment of ionic exchange resins emphasised the requirement of very high temperature on the surface of the glass. When this surface is to cold, the unperfected oxidation lead to a glass containing inclusion such as metallic compounds coming from the reduction of species contained in the waste. Thus, the qua

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16

Gossé, S., C. Guéneau, S. Bordier, S. Schuller, A. Laplace, and J. Rogez. "A Thermodynamic Approach to Predict the Metallic and Oxide Phases Precipitations in Nuclear Waste Glass Melts." Procedia Materials Science 7 (2014): 79–86. http://dx.doi.org/10.1016/j.mspro.2014.10.011.

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17

Niederleithinger, Ernst, Vera Lay, Christian Köpp, Erika Holt, and Maria Oksa. "PREDIS: innovative ways for predisposal treatment and monitoring of low and medium radioactive waste." Safety of Nuclear Waste Disposal 1 (November 10, 2021): 9–10. http://dx.doi.org/10.5194/sand-1-9-2021.

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Abstract. The EURATOM PREDIS project (http://www.predis-h2020.eu, last access: 25 October 2021) targets the development and implementation of activities for predisposal treatment of radioactive waste streams other than nuclear fuel and high-level radioactive waste. It started on 1 September 2020 with a 4 year duration. The consortium includes 47 partners from 17 member states. The overall budget of the project is EUR 23.7 million, with EC contribution of EUR 14 million. The PREDIS project develops and increases the technological readiness level (TRL) of treatment and conditioning methodologies

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18

Guillaume, D., A. Neaman, M. Cathelineau, et al. "Experimental synthesis of chlorite from smectite at 300ºC in the presence of metallic Fe." Clay Minerals 38, no. 3 (2003): 281–302. http://dx.doi.org/10.1180/0009855033830096.

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AbstractThe alteration and transformation behaviour of montmorillonite (bentonite from Wyoming, MX-80) in low-salinity solutions (NaCl, CaCl2) in the presence of metallic Fe (powder and 86461 mm plate) and magnetite powder was studied in batch experiments at 300ºC to simulate the mineralogical and chemical reactions of clays in contact with steel in a nuclear waste repository. The evolutions of pH and solution concentrations were measured over a period of 9 months. The mineralogical and chemical evolution of the clays was studied by XRD, SEM, Transmission Mössbauer Spectroscopy and TEM (EDS, H

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19

Orr, Robin, Hugh Godfrey, Chris Broan, et al. "Formation and physical properties of uranium hydride under conditions relevant to metallic fuel and nuclear waste storage." Journal of Nuclear Materials 477 (August 2016): 236–45. http://dx.doi.org/10.1016/j.jnucmat.2016.04.057.

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20

Paraskevoulakos, C., C. A. Stitt, K. R. Hallam, et al. "Monitoring the degradation of nuclear waste packages induced by interior metallic corrosion using synchrotron X-ray tomography." Construction and Building Materials 215 (August 2019): 90–103. http://dx.doi.org/10.1016/j.conbuildmat.2019.04.178.

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21

Buck, Edgar C., Alan L. Schemer-Kohrn, and Jonathan B. Wierschke. "Technetium Incorporation into C14 and C15 Laves Intermetallic Phases." MRS Proceedings 1518 (2013): 117–22. http://dx.doi.org/10.1557/opl.2013.69.

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ABSTRACTLaves-type intermetallic phases have been observed to be the dominant phases in a series of alloy compositions being designed for the immobilization of technetium in a metallic waste form. The dominant metals in the alloy compositions were Fe-Mo and Fe-Mo-Zr. The alloy composition, Fe-Mo-Zr, also contained Pd, Zr, Cr, and Ni. Both non-radioactive rhenium-containing and radioactive technetium-bearing alloy compositions were investigated. In the Fe-Mo series, the phases observed were Fe2Mo (C14 Laves phase) and ferrite in agreement with predictions. Both Tc and Re resided predominantly i

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22

TOKUHIRO, Tadashi, Joshua W. CAREY, Rolanda M. REED, and Sita S. AKELLA. "SELECTIVE CAPTURE AND ENCAPSULATION OF METALLIC CATIONS BY HYDROGELS CONSISTING OF COPOLY(N-ISOPROPYLACRYLAMIDE/FUNCTIONAL MONOMER) NETWORKS." SOUTHERN BRAZILIAN JOURNAL OF CHEMISTRY 20, no. 20 (2012): 25–41. http://dx.doi.org/10.48141/sbjchem.v20.n20.2012.29_revista_2012a.pdf.

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Under the U.S. Department of Energy Waste Treatment Baseline and Integrated Waste Management Strategy the recycling of spent nuclear fuel to minimize waste, to assure maximum energy recovery, and to pursue science-based R&D to possibly eliminate the need for geologic waste repositories, are programmatic goals. We have developed both polymer gel and porous materials for the separation and adsorption of targeted contaminants. Here, we have investigated capture and encapsulation capabilities of hydrogels consisting of thermally-sensitive copoly[N-isopropylacrylamide(1-x) / functional monomer(

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23

Chaudhry, Muhammad Junaid, Sascha Gentes, Alexander Heneka, and Carla Olivia Krauß. "Wet sieving and magnetic separation for the treatment of radioactive secondary waste produced from waterjet abrasive suspension cutting." Safety of Nuclear Waste Disposal 2 (September 6, 2023): 9–10. http://dx.doi.org/10.5194/sand-2-9-2023.

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Abstract. Dismantling of reactor pressure vessels and their built-in components is an enormous challenge in the deconstruction of a nuclear power plant. Due to the years of exposure to neutron radiation, the activated components can only be dismantled and packaged remotely. For reasons of radiation protection, preference is given to techniques that can be used underwater due to the shielding effect. A cutting method that meets these requirements is the waterjet abrasive suspension cutting technique (WAS). The cutting tool is capable of slicing metallic internals and other materials using a pur

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24

Fujita, Reiko, Mitsuaki Yamaoka, Masatoshi Kawashima, Masaki Saito, Haruaki Matsuura, and Hiroshi Akatsuka. "A metallic fuel cycle for Self-Consistent Nuclear Energy System (SCNES)." Progress in Nuclear Energy 40, no. 3-4 (2002): 615–20. http://dx.doi.org/10.1016/s0149-1970(02)00057-4.

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25

Guo, Xiaolei, Penghui Lei, Chandi Mohanty, Tiankai Yao, Jie Lian, and Gerald S. Frankel. "Enhanced Crevice Corrosion of Stainless Steel 316 By Degradation of Cr-Containing Hollandite Crevice Former." ECS Meeting Abstracts MA2022-02, no. 11 (2022): 739. http://dx.doi.org/10.1149/ma2022-0211739mtgabs.

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The disposal of high-level nuclear waste (HLW) is an important societal problem. It is also an extremely challenging corrosion research topic due to the highly complicated waste chemistry, long lasting radiation effect, and inevitable exposure to aqueous environments for hundreds of thousands of years. To safely accommodate some critical radionuclides such as volatile 129I and strongly heat generating 137Cs, numerous crystalline ceramic waste forms have been created and studied. Among the promising nuclear waste forms, hollandite was developed to isolate Cs waste and the corresponding decay pr

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Osacký, Marek, Miroslav Honty, Jana Madejová, Thomas Bakas, and Vladimír Šucha. "Experimental interactions of Slovak bentonites with metallic iron." Geologica Carpathica 60, no. 6 (2009): 535–43. http://dx.doi.org/10.2478/v10096-009-0039-7.

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Experimental interactions of Slovak bentonites with metallic ironThe experimental stability of four bentonites and one K-bentonite from Slovak deposits in the presence of iron was studied to simulate the possible reactions of clays (bentonite barrier) in the contact with Fe containers in a nuclear waste repository. The batch experiments were performed at 60 °C for 30 and 120 days in aerobic conditions. The reaction products were examined by XRD, FTIR, and Mössbauer spectroscopies and CEC (cation exchange capacities) were determined. Reaction solutions were analysed for selected elements using

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Pokhitonov, Yu A., V. A. Starchenko, I. Yu Dalyaev, and S. L. Titov. "Using hot isostatic pressing for radioactive waste isolation purposes." Radioactive Waste 16, no. 3 (2021): 20–29. http://dx.doi.org/10.25283/2587-9707-2021-3-20-29.

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The paper summarizes the findings of a study focused on hot isostatic pressing (HIP) technique implemented by the Khlopin Radium institute. The equipment was designed and manufactured at the Kharkov’s Physics and Technology Institute. The installation provided a pressure of up to 400 NPa with the pressing temperature of up to 1250°C. The experiments were carried out on installations located in hot cells in the radiochemical department (Gatchina city). Samples of materials for HLW immobilization (titanate ceramics of the synroc type, stabilized cubic zirconia) and matrices for 129I immobilizati

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Haas, Allan, Dale F. Rucker, and Marc T. Levitt. "Investigating the effective resistivity of reinforced concrete waste storage tanks at the Hanford Site." GEOPHYSICS 87, no. 1 (2021): B31—B43. http://dx.doi.org/10.1190/geo2021-0187.1.

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Industrialized sites pose challenges for conducting electrical resistivity geophysical surveys because the sites typically contain metallic infrastructure that can mask electrolytic-based soil and groundwater contamination. The Hanford Nuclear Site in eastern Washington State, USA, is an industrialized site with underground storage tanks, piping networks, steel fencing, and other potentially interfering infrastructure that could inhibit the effectiveness of electrical resistivity tomography (ERT) to map historical and monitor current waste releases. The underground storage tanks are the larges

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Khorasanov, Georgiy, Dmitriy Samokhin, Aleksandr Zevyakin, Yevgeniy Zemskov, and Anatoliy Blokhin. "Lead reactor of small power with metallic fuel." Nuclear Energy and Technology 4, no. 2 (2018): 99–102. http://dx.doi.org/10.3897/nucet.4.30527.

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The possibility for obtaining a hard neutron spectrum in small reactor cores has been considered. A harder spectrum than spectra in known fast sodium cooled and molten salt reactors has been obtained thanks to the selection of relatively small core dimensions and the use of metallic fuel and natural lead (natPb) coolant. The calculations for these compositions achieve an increased average neutron energy and a large fraction of hard neutrons in the spectrum (with energies greater than 0.8 MeV) caused by a minor inelastic interaction of neutrons with the fuel with no light chemical elements and

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Voronkova, Liubov V. "Recent Advances in Cast Iron Structure and Properties Ultrasonic Testing and Flaw Detection." Materials Science Forum 925 (June 2018): 499–503. http://dx.doi.org/10.4028/www.scientific.net/msf.925.499.

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The advantage of ultrasonic testing of iron castings prior to destructive control consists of an impressive reduction in time and costs, as well as the ability to assess the quality of the metal anywhere on the castings. According to the acoustic characteristics of cast iron it is possible to determine the form of graphite in it and its strength. The presence of chill in the metallic base and the thickness of the chilled layer is also determined by ultrasonic method. The use of electronic signal processing allows to distinguish it from high structural noise, which makes possible the testing of

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Grigaliūnienė, Dalia, Robertas Poškas, Raimondas Kilda, Hussam Jouhara, and Povilas Poškas. "Modeling radionuclide migration from activated metallic waste disposal in a generic geological repository in Lithuania." Nuclear Engineering and Design 370 (December 2020): 110885. http://dx.doi.org/10.1016/j.nucengdes.2020.110885.

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Siddiqui, N. A., M. A. Iqbal, H. Abbas, and D. K. Paul. "Reliability analysis of nuclear containment without metallic liners against jet aircraft crash." Nuclear Engineering and Design 224, no. 1 (2003): 11–21. http://dx.doi.org/10.1016/s0029-5493(03)00080-3.

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Gebauer, Jana, Florian Gruber, Wilhelm Holfeld, Wulf Grählert, and Andrés Fabián Lasagni. "Prediction of the Quality of Thermally Sprayed Copper Coatings on Laser-Structured CFRP Surfaces Using Hyperspectral Imaging." Photonics 9, no. 7 (2022): 439. http://dx.doi.org/10.3390/photonics9070439.

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With the progressive replacement of metallic parts by high-performance fiber-reinforced plastic (FRP) components, typical properties of metals are required to be placed on the material’s surface. A metallic coating applied to the FRP surface by thermal spraying, for instance, can fulfill these requirements, including electrical conductivity. In this work, laser pre-treatments are utilized for increasing the bond strength of metallic coatings. However, due to the high-precision material removal using pulsed laser radiation, the production-related heterogeneous fiber distribution in FRP leads to

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Rucker, Dale F., Meng H. Loke, Marc T. Levitt, and Gillian E. Noonan. "Electrical-resistivity characterization of an industrial site using long electrodes." GEOPHYSICS 75, no. 4 (2010): WA95—WA104. http://dx.doi.org/10.1190/1.3464806.

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An electrical-resistivity survey was completed at the T tank farm at the Hanford nuclear site in Washington State, U.S.A. The purpose of the survey was to define the lateral extent of waste plumes in the vadose zone in and around the tank farm. The T tank farm consists of single-shell tanks that historically have leaked and many liquid-waste-disposal facilities that provide a good target for resistivity mapping. Given that the site is highly industrialized with near-surface metallic infrastructure that potentially could mask any interpretable waste plume, it was necessary to use the many wells

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Parsons, Sam, Thomas Haines, Matthew White, et al. "Features, events and processes (FEP) analysis of the interactions between repository monitoring systems and multi-barrier systems." Safety of Nuclear Waste Disposal 2 (September 6, 2023): 177–78. http://dx.doi.org/10.5194/sand-2-177-2023.

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Abstract. In line with the European waste directive 2011/70/EURATOM, the European Joint Programme on Radioactive Waste Management (EURAD) was launched in June 2019. EURAD aims to make a step change in European collaboration between advanced and early-stage waste management programmes. Monitoring Equipment and Data Treatment for Safe Repository Operation and Staged Closure (MODATS) is Work Package (WP) 17 of the EURAD programme. This WP aims to address a range of research needs relating to repository monitoring data and technologies. This abstract summarises research relating to the interaction

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Law, Kathleen A., Stephen Parry, Nicholas D. Bryan, et al. "Plutonium Migration during the Leaching of Cemented Radioactive Waste Sludges." Geosciences 9, no. 1 (2019): 31. http://dx.doi.org/10.3390/geosciences9010031.

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One of the most challenging components of the UK nuclear legacy is Magnox sludge, arising from the corrosion of Mg alloy-clad irradiated metallic U fuel that has been stored in high pH ponds. The sludges mainly comprise Mg hydroxide and carbonate phases, contaminated with fission products and actinides, including Pu. Cementation and deep geological disposal is one option for the long-term management of this material, but there is a need to understand how Pu may be leached from the waste, if it is exposed to groundwater. Here, we show that cemented Mg(OH)2 powder prepared with Pu(IV)aq is alter

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Paraskevoulakos, C., K. R. Hallam, and T. B. Scott. "Grout durability within miniaturised Intermediate Level Waste drums at early stages of interior volume expansion induced by encapsulated metallic corrosion." Journal of Nuclear Materials 510 (November 2018): 348–59. http://dx.doi.org/10.1016/j.jnucmat.2018.08.028.

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Galliez, Kévin, Guillaume Jossens, Alain Godot, and Christophe Mathonat. "Characterization of Low Level Wastes: a new design for calorimetric measurement." EPJ Web of Conferences 170 (2018): 07003. http://dx.doi.org/10.1051/epjconf/201817007003.

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Calorimetry is one of the best solutions to estimate the overall quantity of nuclear material on a wide range of masses, from a few milligrams up to kilograms of radionuclides, by measuring the overall thermal power due to the radioactive decay coming from the waste contained in a metallic drum or a different type of container. It has many advantages as it features a non-destructive method which remains independent of matrix effect or the chemical composition. Until now, calorimetry allows to measure at the lowest 0.5 to 1 mW for samples up to 385 liters. But nowadays, thanks to new technologi

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Kuzina, Yu, D. Klinov, G. Mikhailov, A. Sorokin, and V. Alekseev. "COMPLEX OF EXPERIMENTAL FACILITIES FOR DESIGN AND SAFETY JUSTIFICATION OF FAST REACTORS WITH LIQUID METAL COOLANTS." PROBLEMS OF ATOMIC SCIENCE AND TECHNOLOGY. SERIES: NUCLEAR AND REACTOR CONSTANTS 2021, no. 4 (2021): 172–94. http://dx.doi.org/10.55176/2414-1038-2021-4-172-194.

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To substantiate the safety and characteristics of fast reactors with liquid metal coolants, a complex of more than 20 stands of various profiles and purposes, well equipped with modern measuring instruments, including hydrodynamic, thermohydraulic and technological stands, has been created at SSC RF - IPPE. In addition, JSC “SSC RF - IPPE” has a complex of fast physical stands, including two critical stands - BFS-1 and the world's largest physical stand BFS-2. The article presents the characteristics and the possibility of stands designed for research in the field of hydrodynamics, heat transf

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Okunev, Viacheslav. "The concept of a fast reactor with liquid metal fuel in tungsten capsules." E3S Web of Conferences 411 (2023): 01013. http://dx.doi.org/10.1051/e3sconf/202341101013.

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The concept of a dual-purpose high-power nuclear reactor is proposed. One of the goals is the production of electricity, the other is the production of high-potential thermal energy. It is proposed to use liquid fuel based on waste uranium and plutonium extracted from the spent fuel of VVER reactors (purified from the 238Pu isotope). The fuel is in sealed tungsten capsules. Lead extracted from thorium ores is used to cool the reactor. The electrical power of the reactor is 3.3 GW. The layout of the reactor is identical to the BREST-OD-300 reactor under construction. The analysis of emergency m

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Ben-Dor, G., A. Dubinsky, and T. Elperin. "Optimization of multi-layered metallic shield." Nuclear Engineering and Design 241, no. 6 (2011): 2020–25. http://dx.doi.org/10.1016/j.nucengdes.2011.01.046.

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Pasquato, Leone, Christoph Strangfeld, Esko Strömmer, et al. "Embedded sensors system to monitor cemented waste drums." Safety of Nuclear Waste Disposal 2 (September 6, 2023): 21. http://dx.doi.org/10.5194/sand-2-21-2023.

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Abstract. BAM (Federal Institute for Materials Research and Testing) is developing an electronic measurement system to be placed inside a waste drum, which will be filled with concrete. The goal of this measurement system is to monitor the process of hardening and the evolution of the concrete itself over time to indirectly identify potential defects such as corrosion or cracking. The measured parameters are humidity, temperature, and pressure. In this regard, particular attention was given to the design of the electronic board's enclosure, to allow the sensors to measure the state of the conc

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Bieniussa, K. W. "German codes and standards concerning metallic nuclear power plant components — Present state and trends expected." Nuclear Engineering and Design 98, no. 3 (1987): 279–81. http://dx.doi.org/10.1016/0029-5493(87)90004-5.

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Tachibana, Yukio, and Tatsuo Iyoku. "Structural design of high temperature metallic components." Nuclear Engineering and Design 233, no. 1-3 (2004): 261–72. http://dx.doi.org/10.1016/j.nucengdes.2004.08.013.

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Sulatsky, Andrey A., Viacheslav I. Almjashev, Vladimir S. Granovsky, et al. "Experimental study of oxidic-metallic melt oxidation." Nuclear Engineering and Design 363 (July 2020): 110618. http://dx.doi.org/10.1016/j.nucengdes.2020.110618.

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Rothfuss, Helmut, Dieter Stausebach, and Manfred Ullrich. "Metallic core internals of the modular HTR." Nuclear Engineering and Design 147, no. 1 (1994): 93–100. http://dx.doi.org/10.1016/0029-5493(94)90260-7.

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Xie, Yi, Jinsuo Zhang, Xiang Li, et al. "Lanthanide migration and immobilization in metallic fuels." Progress in Nuclear Energy 109 (November 2018): 233–38. http://dx.doi.org/10.1016/j.pnucene.2018.08.019.

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Ebert, Elena L., Andrey Bukaemskiy, Fabian Sadowski, Steve Lange, Andreas Wilden, and Giuseppe Modolo. "Reprocessability of molybdenum and magnesia based inert matrix fuels." Nukleonika 60, no. 4 (2015): 871–78. http://dx.doi.org/10.1515/nuka-2015-0124.

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Abstract This work focuses on the reprocessability of metallic 92Mo and ceramic MgO, which is under investigation for (Pu,MA)-oxide (MA = minor actinide) fuel within a metallic 92Mo matrix (CERMET) and a ceramic MgO matrix (CERCER). Magnesium oxide and molybdenum reference samples have been fabricated by powder metallurgy. The dissolution of the matrices was studied as a function of HNO3 concentration (1-7 mol/L) and temperature (25-90°C). The rate of dissolution of magnesium oxide and metallic molybdenum increased with temperature. While the MgO rate was independent of the acid concentration

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., Manisha, Anima Sunil Dadhich, and Anik Sen. "Preparation of barium ferrate from mill scale and degradation study of aqueous Eriochrome black – T." Research Journal of Chemistry and Environment 27, no. 2 (2023): 10–19. http://dx.doi.org/10.25303/2702rjce10019.

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This present study involves the utilization of mill scale, an iron rich steel industry waste, to synthesize barium ferrate. Ferrate with iron in +(VI) oxidation state is a green chemical with promising oxidation, disinfection and coagulation properties. The X-Ray diffraction(XRD) analysis of mill scale indicates the presence of iron in three forms hematite, magnetite and wustite. Mill scale was dissolved in concentrated HCl. The metallic composition of dissolved mill scale was determined by Inductively Couple Plasma Mass Spectroscopy(ICP-MS). Barium ferrate was synthesized using the dissolved

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Yacout, Abdellatif M., Kun Mo, Aaron Oaks, Yinbin Miao, Tanju Sofu, and Walid Mohamed. "FIPD: The SFR metallic fuels irradiation & physics database." Nuclear Engineering and Design 380 (August 2021): 111225. http://dx.doi.org/10.1016/j.nucengdes.2021.111225.

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