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Journal articles on the topic 'Final storage of radioactive waste'

Author: Grafiati

Published: 4 June 2021

Last updated: 8 February 2022

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1

Glasser, F. P., and M. Atkins. "Cements in Radioactive Waste Disposal." MRS Bulletin 19, no. 12 (1994): 33–38. http://dx.doi.org/10.1557/s0883769400048673.

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Depending on their radioactive content and abundance of long-lived radionuclides, radioactive wastes are often described as low, intermediate or high-level. Cements play a major role in the engineered structures, existing and planned, of most national programs for low- and intermediate-level (ILW) radioactive wastes. Final disposal of ILW is usually by burial at considerable depth (>250 meters), e.g., in planned repositories in clay at Mol (Belgium), in salt at Gorleben (Germany), and in volcanic tuffs at Sellafield (United Kingdom). A sample disposal concept is shown in Figure 1. Shallow l

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2

Neubauer, Josef. "Radioactive waste management in Austria." Nuclear Technology and Radiation Protection 19, no. 2 (2004): 59–64. http://dx.doi.org/10.2298/ntrp0402059n.

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At the Austrian Research Centers Seibersdorf, there are several facilities in stalled for treatment of waste of low and intermediate radioactivity level (radwaste). A separate company within Centers, Nuclear Engineering Seibersdorf, has been formed recently, acting as a centralized facility for treatment, conditioning and storing of such waste within the country. The relevant treatment technology is applied depending on the waste category. In total about 6900 m3 of solid waste of low and intermediate radioactivity level originating from Austria was treated in the period between 1976 and 2002.

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3

Iarmosh, I., S. Kondratiev, L. Kuechler, O. Tokarevskyi, and O. Solovyov. "Approaches to characterization of radioactive waste in Ukraine at interrelated steps of their management." Nuclear and Radiation Safety, no. 1(85) (March 13, 2020): 41–49. http://dx.doi.org/10.32918/nrs.2020.1(85).04.

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A key point for safety assessments at different steps of radioactive waste (RW) management is the knowledge of all the relevant properties of materials that are to be disposed of as RW or cleared from regulatory control (immediately or after a certain period of time for decay storage). Characterization is the basis for the determination of radiological and non-radiological hazards of the radioactive materials and waste. This paper considers approaches for a systemized characterization of radioactive waste at all steps of its management from generation to disposal. These approaches ensure

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4

Ojovan, Michael I., Rebecca A. Robbins, and Miklos Garamszeghy. "Advances in conditioning of low- and intermediate-level nuclear waste." MRS Advances 3, no. 19 (2017): 983–90. http://dx.doi.org/10.1557/adv.2017.613.

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ABSTRACTRadioactive waste with widely varying characteristics is generated from the operation and maintenance of nuclear reactors, nuclear fuel cycle facilities, research facilities and medical facilities and the through the use of radioisotopes in industrial applications. The waste needs to be treated and conditioned appropriately to provide wasteforms acceptable for safe storage and disposal. Conditioning of radioactive waste is an important step to prepare waste for long-term storage or disposal and includes the following processes:▪ Immobilization which may or may not also provide volume r

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5

Rosnovsky, Sergey V., and Vladimir P. Povarov. "Ensuring radiation safety during temporary storage of solidified radioactive waste in light hangar-type facilities." Nuclear Energy and Technology 7, no. 3 (2021): 195–99. http://dx.doi.org/10.3897/nucet.7.73487.

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Expensive permanent storage facilities with massive engineered structures are used traditionally to ensure safe temporary storage of solidified radioactive waste at the NPP sites. Such approach is dictated by the need to comply with the regulatory requirements for limiting the gamma background in the area adjacent to the storage facility. The costs involved in temporary storage of solidified RW can be optimized by using light hangar-type storage facilities. At the same time, the safety of storage, including radiation protection of the personnel, the public and the environment, is undoubtedly e

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6

Stefanovsky, Sergey V., Yuri V. Myshkin, Dmitri V. Adamovich, and Michael D. Beliy. "RADON Operational Experience in High-Temperature Treatment of Radioactive Wastes." Advances in Science and Technology 94 (October 2014): 121–30. http://dx.doi.org/10.4028/www.scientific.net/ast.94.121.

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FSUE Radon deals with collection, transportation, treatment, conditioning, and interim storage and final disposal of conditioned low-and intermediate-level radioactive wastes (LILW) as well as radiation monitoring, decontamination and environmental remediation of Moscow and Moscow area. Liquid LILW with high salinity is subject to vitrification at the Radon full scale vitrification plant using a cold crucible inductive melting (CCIM) at temperatures of 1150-1200 °C. The bench-scale cold crucible based unit is used for research works and feasibility study on new promising ceramic and glass-cera

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7

Sanders, Charlotta E. "Review of the Development of the Proposed Yucca Mountain Geologic Repository." Advances in Science and Technology 94 (October 2014): 115–20. http://dx.doi.org/10.4028/www.scientific.net/ast.94.115.

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It can be said that the nuclear community neglected the issue of final storage of nuclear waste in the first era of nuclear power production, with many nations not looking at this topic until some years into its program. This is a matter that must not be neglected now during the ‘renaissance’ of nuclear if nuclear energy is to have a part on the stage of the play in world energy supplies. In 1982, the United States (U.S.) Congress passed the Nuclear Waste Policy Act (NWPA), which outlines the screening process for selecting a national site for used nuclear fuel and high-level radioactive waste

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8

Tantau, Adrian, and Greta-Marilena Vitioanu. "Key factors affecting disposal of radioactive waste in the sustainable development approach." Proceedings of the International Conference on Business Excellence 14, no. 1 (2020): 1–15. http://dx.doi.org/10.2478/picbe-2020-0002.

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AbstractThe radioactive waste disposal is a well investigated issue worldwide because of its importance for a safe and sustainable use of nuclear energy. Such waste is subject to final storage in deep geological disposals. Many factors have a direct contribution to the success of such innovative facility. The objective of the study is to identify the principal factors which contribute to the radioactive waste location. Factors that influence public acceptance are recognized and emphasized in the paper. The methodology is based on a questionnaire for empirical data obtaining and interviews with

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9

Balderer, Werner. "The NAGRA investigation project for the assessment of repositories for high-level radioactive waste in geological formations." Mineralogical Magazine 49, no. 351 (1985): 281–88. http://dx.doi.org/10.1180/minmag.1985.049.351.15.

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AbstractThe first results of isotopic investigations as a part of the hydrogeological study of northern Switzerland are presented. This study is part of the global geological research project of the NAGRA (National Co-operative for the Storage of Radioactive Waste) which is intended to provide the scientific knowledge required for the assessment of the feasibility of safe disposal of highly radioactive waste in the geological formations of the area. The aim of the hydrogeological research programme is to assess the natural conditions in the sedimentary sequence and the underlying granite basem

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10

Hyatt and Ojovan. "Special Issue: Materials for Nuclear Waste Immobilization." Materials 12, no. 21 (2019): 3611. http://dx.doi.org/10.3390/ma12213611.

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Nuclear energy is clean, reliable, and competitive with many useful applications, among which power generation is the most important as it can gradually replace fossil fuels and avoid massive pollution of environment. A by-product resulting from utilization of nuclear energy in both power generation and other applications, such as in medicine, industry, agriculture, and research, is nuclear waste. Safe and effective management of nuclear waste is crucial to ensure sustainable utilization of nuclear energy. Nuclear waste must be processed to make it safe for storage, transportation, and final d

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11

Vahlund, Fredrik. "Long-term safety of the extended SFR - Methodology and conclusions from the SR-PSU project." MRS Advances 1, no. 61 (2016): 4075–80. http://dx.doi.org/10.1557/adv.2017.192.

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ABSTRACTSince 1988 the Swedish Nuclear Fuel and Waste Management Co. operates a repository for low- and intermediate-level short-lived radioactive waste, SFR, in Forsmark, Sweden. Due to decommissioning of the nuclear power plants additional storage capacity is needed. In December 2014, an application to extend the repository was therefore submitted. One key component of this application was an assessment of post-closure safety of the extended SFR. For this safety assessment, a methodology based on that developed by SKB for the spent nuclear fuel repository was used and the impact of the degra

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12

Leunbach, Rosa Nan, and Kristian H. Nielsen. "Exploring the Dialogical Space of Hybrid Forums: The “Predictably Unpredictable” Case of Radioactive Waste Management in Denmark, 2003-2018." Bulletin of Science, Technology & Society 39, no. 1-2 (2019): 4–18. http://dx.doi.org/10.1177/0270467620932831.

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Denmark was once at the forefront of nuclear research, operating three experimental nuclear reactors at the research facility at Risø, close to Copenhagen. However, the 1985 resolution of the Danish Parliament excluded nuclear power from the national energy mix. In 2003, the Parliament passed a resolution on the decommissioning of the nuclear facility at Risø, including plans for establishing a permanent solution for radioactive waste management. To understand the ensuing socio-technical controversy, we employ the “hybrid forum” framework that emphasizes the entangled political-epistemological

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13

Olkhovyk, Yu A. "Perspective Schemes of Conditioning of Liquid Radioactive Waste of Ukrainian Nuclear Power Plants." Nuclear Power and the Environment 18 (2020): 48–56. http://dx.doi.org/10.31717/2311-8253.20.3.6.

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The existing world experience of practical use of sorption technology and technology of cementing liquid borne radioactive waste of nuclear power plants (NPP) with water-water energetic reactors (WWER) to obtain a product 1suitable for transfer to disposal facilities is considered. It has been concluded that salt cake accumulated in NPP storage facilities is a major problem that determines the further choice of the development and implementation of conditioning technologies. Currently, 18,000 salt cake containers stored at the Zaporizhzhia NPP and Khmelnitskiy NPP storage facilities have excee

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14

Paunov, Petar, and Ivaylo Naydenov. "Long-Term Radiotoxicity Evaluation of PWR Spent Uranium and MOX Fuel and Highly Active Waste." E3S Web of Conferences 207 (2020): 01024. http://dx.doi.org/10.1051/e3sconf/202020701024.

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One of the main concerns related to nuclear power production is the generation and accumulation of spent nuclear fuel. Currently most of the spent fuel is stored in interim storage facilities awaiting final disposal or reprocessing. The spent fuel is stored in isolation from the environment in protected facilities or specially designed containers. Nevertheless, spent fuel and highly active waste might get in the environment in case the protective barriers are compromised. In such a case, spent fuel may pose risk to the environment and human health. Those risks depend on the concentration of th

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15

Smart, N. R., R. J. Winsley, P. A. H. Fennell, B. Reddy, A. P. Rance, and C. Padovani. "Waste container durability: monitoring of a stainless steel 4 metre box over 12 years." Mineralogical Magazine 76, no. 8 (2012): 2891–99. http://dx.doi.org/10.1180/minmag.2012.076.8.04.

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AbstractIn the UK, most intermediate level radioactive waste is packaged in stainless steel containers. It is important that containers should maintain their integrity for extended periods of storage prior to final disposal. A prototype 4 metre box fabricated from 304S11 stainless steel was monitored at an inland rural building for over twelve years to gain experience in monitoring environmental conditions and corrosion during storage. A wide range of different types of aerosol particles were observed on the surfaces and in the air. They contained corrosive ions such as chloride, as well as ot

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16

Yaroshenko, K. K., B. G. Shabalin, and G. M. Bondarenko. "Investigation of the processes of organic components ozonolysis of liquid radioactive waste model solutions of VVER reactors." Nuclear Power and the Environment 19, no. 4 (2020): 31–38. http://dx.doi.org/10.31717/2311-8253.20.4.4.

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The article highlights the problem of reprocessing of liquid radioactive waste (LRW) from the Ukrainian nuclear power plants with VVER reactors. The main method of these LRW treatment is distillation (evaporation) and ion exchange sorption. The final products of LRW processing by distillation are distillation residues, spent sorbents and sludges, and salt melt with significant radioactivity accumulated in large volumes, which do not meet the long-term storage and disposal criteria. So, it is necessary to develop a new, more efficient LRW treatment scheme that can solve the problems of large vo

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17

Строкин, А., A. Strokin, А. Валов, and A. Valov. "Treatment of Spent Ion Exchange Resins in Nuclear Industry." Safety in Technosphere 6, no. 3 (2017): 42–47. http://dx.doi.org/10.12737/article_59d496314e8e13.60887752.

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This work is devoted to development of domestic technology for ion exchange resins treatment (conditioning) in the nuclear industry. In the work has been carried out the analysis of a number of domestic technologies applied to treatment of liquid radioactive waste for the purpose of their knots use for developed technological chain’s cost reduction. The analysis of perspective foreign technologies which are already used for ion exchange resins conditioning has been carried out as well. According to analysis report has been proposed the domestic technology for ion exchange resins conditioning w

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18

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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19

Schwenk-Ferrero, A. "German Spent Nuclear Fuel Legacy: Characteristics and High-Level Waste Management Issues." Science and Technology of Nuclear Installations 2013 (2013): 1–11. http://dx.doi.org/10.1155/2013/293792.

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Germany is phasing-out the utilization of nuclear energy until 2022. Currently, nine light water reactors of originally nineteen are still connected to the grid. All power plants generate high-level nuclear waste like spent uranium or mixed uranium-plutonium dioxide fuel which has to be properly managed. Moreover, vitrified high-level waste containing minor actinides, fission products, and traces of plutonium reprocessing loses produced by reprocessing facilities has to be disposed of. In the paper, the assessments of German spent fuel legacy (heavy metal content) and the nuclide composition o

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20

Marty, Nicolas C. M., Sylvain Grangeon, Catherine Lerouge, et al. "Dissolution kinetics of hydrated calcium aluminates (AFm-Cl) as a function of pH and at room temperature." Mineralogical Magazine 81, no. 5 (2017): 1245–59. http://dx.doi.org/10.1180/minmag.2016.080.161.

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AbstractThe determination of reliable weathering/dissolution rates for cement phases is of fundamental importance for the modelling of the temporal evolution of both radioactive waste repositories and CO2 geological storage sites (e.g. waste matrix, plug in boreholes). Here, the dissolution kinetics of AFm-Cl (hydrated calcium aluminates containing interlayer Cl) has been studied using flow-through experiments conducted at pH values ranging from 9.2 to 13. Mineralogical (XRD) and chemical (EPMA, TEM) analyses have been performed to determine the evolution of the phases during the dissolution e

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21

Zihms, S. G., and J. F. Harrington. "Thermal cycling: impact on bentonite permeability." Mineralogical Magazine 79, no. 6 (2015): 1543–50. http://dx.doi.org/10.1180/minmag.2015.079.6.29.

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AbstractDue to its favourable properties, in particular, low permeability and swelling capacity, bentonite has been favoured as an engineered-barrier and backfill material for the geological storage of radioactive waste. To ensure its safe long-term performance it is important to understand any changes in these properties when the material is subject to heat-emitting waste. As such, this study investigates the hydraulic response of bentonite under multi-step thermal loading subject to a constant-volume boundary condition, to represent a barrier system used in a crystalline or other hard-rock h

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22

Tokarevskyi, O., K. Fuzik, S. Kondratiev, and Z. Alekseeva. "Analysis of Safety Aspects of Disused Sealed Radiation Source Disposal." Nuclear and Radiation Safety, no. 2(86) (June 12, 2020): 72–80. http://dx.doi.org/10.32918/nrs.2020.2(86).09.

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Sealed radiation sources (SRS) are extensively used worldwide in agriculture, industry, medicine and different research areas. If further use of SRS is not envisaged, and the decision is made on declaration of these disused SRSs (DSRS) as radioactive waste (RW), then legislative and regulatory requirements for RW management are fully applicable from that point. Since DSRSs have essential distinctions from other types of RW, in particular, high specific activity, it is critically important to ensure safe management of DSRS, declared as RW, at all stages of their management including

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23

Marsiske, Maximilian R., Christian Debus, Fulvio Di Lorenzo, Ellina Bernard, Sergey V. Churakov, and Cristina Ruiz-Agudo. "Immobilization of (Aqueous) Cations in Low pH M-S-H Cement." Applied Sciences 11, no. 7 (2021): 2968. http://dx.doi.org/10.3390/app11072968.

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Incorporation of heavy metal ions in cement hydrates is of great interest for the storage and immobilization of toxic, hazardous, and radioactive wastes using cementitious matrix. Magnesium silicate hydrate (M-S-H) is a low pH alternative cementitious binder to commonly used Portland cement. Low pH cements have been considered as promising matrix for municipal and nuclear waste immobilization in the last decades. It is however crucial to assure that the incorporation of secondary ions is not detrimental for the formation of the hydration products. Herein, we investigate the early stages of for

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24

Fuller, E. "Radioactive Waste Storage." Science 268, no. 5215 (1995): 1262–63. http://dx.doi.org/10.1126/science.268.5215.1262-a.

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25

Tsyganchuk, O. M. "State sanitary and anti-epidemic rules and norms of medical waste management." Infusion & Chemotherapy, no. 3.2 (December 15, 2020): 300–302. http://dx.doi.org/10.32902/2663-0338-2020-3.2-300-302.

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Background. Hands are a favorable environment for bacterial colonization. The microflora of skin is divided into resident and transient. The latter gets to the hands of healthcare workers (HCW) by the contact during professional activities during various diagnostic and treatment procedures, as well as by the contact with contaminated objects. General requirements for hand hygiene include short nails, absence of false nails, absence of infected skin injuries (or covered injuries) on the hands and forearms, absence of jewelry or watch. If there is visible dirt, the hands should be washed with us

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26

von Schenck, Henrik, Ulrik Kautsky, Björn Gylling, Elena Abarca, and Jorge Molinero. "Advancing the Modelling Environment for the Safety Assessment of the Swedish LILW Repository at Forsmark." MRS Proceedings 1744 (2015): 223–28. http://dx.doi.org/10.1557/opl.2015.348.

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ABSTRACTAn extension of the Swedish final repository for short-lived radioactive waste (SFR) is planned and a safety assessment has been performed as part of the licensing process. Within this work, steps have been taken to advance the modelling environment to better integrate its individual parts. It is desirable that an integrating modelling environment provides the framework to set up and solve a consistent hierarchy of models on different scales. As a consequence, the consistent connection between software tools and models needs to be considered, related to the full assessment domain. It s

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27

Chen, Y. C., Y. S. Yu, R. S. Chen, I.-Hsin Chou, H. M. Sun, and K. C. Yeh. "Intelligent Radioactive Waste Management Platform for Radioactive Waste Storage Facilities." Nuclear Technology 182, no. 3 (2013): 358–68. http://dx.doi.org/10.13182/nt13-a16985.

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28

Butler, G., and C. Curtis. "Passive storage of radioactive waste." Nuclear Energy 42, no. 3 (2003): 157–62. http://dx.doi.org/10.1680/nuen.42.3.157.37615.

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29

Dellamano, Jos?? Claudio, and Gian-Maria A. A. Sordi. "Optimization of Radioactive Waste Storage." Health Physics 92, Suppl 1 (2007): S27—S36. http://dx.doi.org/10.1097/01.hp.0000252818.20697.1b.

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30

Murray, R. L. "Radioactive waste storage and disposal." Proceedings of the IEEE 74, no. 4 (1986): 552–79. http://dx.doi.org/10.1109/proc.1986.13505.

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31

Freiesleben, H. "Final disposal of radioactive waste." EPJ Web of Conferences 54 (2013): 01006. http://dx.doi.org/10.1051/epjconf/20135401006.

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32

Dran, J. C. "Radiation Effects in Radioactive Waste Storage Materials." Solid State Phenomena 30-31 (January 1992): 367–78. http://dx.doi.org/10.4028/www.scientific.net/ssp.30-31.367.

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33

Richardson, John A. "Storage of High-Level Radioactive Nuclear Waste." Proceedings of the Institution of Mechanical Engineers, Part A: Journal of Power and Energy 216, no. 2 (2002): i—ii. http://dx.doi.org/10.1177/095765090221600201.

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Yamagishi, Isao, Ryuji Nagaishi, Chiaki Kato, et al. "Characterization and storage of radioactive zeolite waste." Journal of Nuclear Science and Technology 51, no. 7-8 (2014): 1044–53. http://dx.doi.org/10.1080/00223131.2014.924446.

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35

Manocchi, F. H., M. P. Campos, J. C. Dellamano, and G. M. Silva. "Radon exposure at a radioactive waste storage facility." Journal of Radiological Protection 34, no. 2 (2014): 339–46. http://dx.doi.org/10.1088/0952-4746/34/2/339.

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36

Savage, David, Jane E. Robbins, and Richard J. Merriman. "Hydrothermal crystallization of a radioactive waste storage glass." Mineralogical Magazine 49, no. 351 (1985): 195–201. http://dx.doi.org/10.1180/minmag.1985.049.351.06.

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AbstractA borosilicate glass, containing 25 wt. % of simulated high-level radioactive waste has been reacted with water at 350°C and 500 bars for 14 and 48 days using large-volume ‘cold-seal’ high-pressure equipment. Under these conditions the glass crystallizes a suite of mineral phases including: albite, NaAlSi3O8; aegirine, NaFeSi2O6; riebeckite, Na2Fe2(Fe,Mg)3Si8O22(OH)2; zektzerite, LiNaZrSi6O15; barium-strontium molybdate, (Ba,Sr)MoO4; stillwellite, (Nd,Ce,La)BSiO5; willemite, Zn2SiO4; smectite; a lithium-sodium borosilicate hydrate; melilite (åkermanite), Ca2MgSi2O7. A description of th

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37

Ogata, Yoshimune, and Kunihide Nishizawa. "Stirring System for Radioactive Waste Water Storage Tank." Health Physics 77, no. 1 (1999): 89–96. http://dx.doi.org/10.1097/00004032-199907000-00014.

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38

Abulfaraj, Waleed H., Tamim A. Samman, and Salah El-Din M. Kamal. "Design of a temporary radioactive waste storage facility." Radiation Physics and Chemistry 44, no. 1-2 (1994): 149–56. http://dx.doi.org/10.1016/0969-806x(94)90121-x.

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39

Warnecke, Ernst, and Reinhard Odoj. "International Seminar on Final Disposal of Radioactive Waste." MRS Bulletin 10, no. 5 (1985): 30–31. http://dx.doi.org/10.1557/s088376940004029x.

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40

Zhemzhurov, M. L., N. D. Kuzmina, A. V. Kuzmin, and K. A. Yarashevich. "Radioactive Waste Activity Resources Estimation at "Ecores" Storage Facilities." Nonlinear Phenomena in Complex Systems 23, no. 4 (2020): 414–27. http://dx.doi.org/10.33581/1561-4085-2020-23-4-414-427.

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In this paper, an estimation of radioactive waste activity resources in mothballed and being decommissioned storage facilities of the special enterprise for radioactive waste management, Unitary Enterprise "Ekores" (The Republic of Belarus), has been carried out taking into account the results of work on their comprehensive engineering and radiation research. At the same time, activity resources are differentiated by radioactive waste categories, what will serve as the basis for development of conceptual technological solutions for their extraction from storage facilities and long-term safety

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41

Kulagina, T. A., and V. A. Kulagin. "Aluminosilicate Sediment Dissolution in Liquid Radioactive Waste Storage Facilities." Radioactive Waste 11, no. 2 (2020): 75–84. http://dx.doi.org/10.25283/2587-9707-2020-2-75-84.

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The article deals with the extraction of insoluble sediments formed in storage tanks during long-term storage of liquid radioactive waste from spent nuclear fuel reprocessing. Results of a thermodynamic analysis are presented enabling to assess the structure of the precipitation formed and to select most effective modes for thermal and hydrodynamic effects (cavitation technology) produced by liquid medium on eroded sediments. The paper presents the results of studies on the extraction of poorly soluble pulp components from storage tanks using cavitation technology.

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42

Podlutskii, M. S., S. N. Lukashenko, A. V. Tomson, and A. A. Oudalova. "Study of tritium nearby a regional radioactive waste storage." Journal of Physics: Conference Series 1701 (November 2020): 012008. http://dx.doi.org/10.1088/1742-6596/1701/1/012008.

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43

Ershov, B. G., and I. M. Kosareva. "Modern state of underground storage of liquid radioactive waste." Russian Journal of General Chemistry 81, no. 9 (2011): 2007–17. http://dx.doi.org/10.1134/s1070363211090477.

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44

Kashcheev, V. A., P. P. Polu�ktov, and A. S. Polyakov. "Possible escape of radionuclides from radioactive waste storage sites." Soviet Atomic Energy 65, no. 3 (1988): 768–73. http://dx.doi.org/10.1007/bf01123021.

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Liland, A., P. Strand, I. Amundsen, et al. "Advances in NORM management in Norway and the application of ICRP's 2007 Recommendations." Annals of the ICRP 41, no. 3-4 (2012): 332–42. http://dx.doi.org/10.1016/j.icrp.2012.06.021.

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In Norway, the largest reported quantities of radioactive discharges and radioactive waste containing naturally occurring radioactive material (NORM) come from the oil and gas sector, and smaller quantities of other NORM waste are also produced by industrial or mining processes. The Gulen final repository for radioactive waste from the oil and gas industry from the Norwegian continental shelf was opened in 2008 and has a capacity of 6000 tonnes. As of 1 January 2011, a new regulation was enforced whereby radioactive waste and radioactive pollution was integrated in the Pollution Control Act fr

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Dikova, L. A., G. M. Minzhanova, and V. A. Makarova. "REVIEW OF FOREIGN PRACTICES FOR RADIOACTIVE WASTE MANAGEMENT." NNC RK Bulletin, no. 1 (May 1, 2021): 68–72. http://dx.doi.org/10.52676/1729-7885-2021-1-68-72.

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The article discusses the experience of foreign countries in the management of radioactive waste of low and medium activity. The main emphasis is placed on the construction and technical solutions of operated near-surface storage / disposal sites. Based on the results of the analysis, it was concluded that the optimal location for near-surface storage facilities are operating radiation hazardous facilities.

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Brodén, K., and G. Olsson. "Final disposal possibilities of radioactive waste components from ITER." Fusion Engineering and Design 69, no. 1-4 (2003): 695–97. http://dx.doi.org/10.1016/s0920-3796(03)00096-6.

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Smetnik, Alexander. "Long-Term Storage and Radioactive Waste Retrieval from Historical Radon-Type Storage Facility." MRS Advances 5, no. 5-6 (2019): 283–91. http://dx.doi.org/10.1557/adv.2019.479.

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ABSTRACTWithin the framework of the IAEA project “CRAFT” (2011-2014), specialists of JSC “VO “Safety” participated in working group “Safety assessment of the Radon-type facilities”. The IAEA GSG-3 methodology was used in order to address the issue of safety assessment of radioactive waste removal from historical near-surface storage facility of the Radon type. SAFRAN tool (Sweden) was used for safety assessment of a historical Radon type storage facility. Practical experience of SAFRAN application has shown that it can play a significant role in managing records and knowledge on radioactive wa

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Kovalenko, V., and O. Gorbunova. "TECHNOLOGICAL DEVELOPMENT OF FSUE "RosRAO" AS A PART OF THE INDUSTRY-SPECIFIC INFRASTRUCTURE FOR PROCESSING, CONDITIONING AND STORAGE OF RADIOACTIVE WASTE." Fine Chemical Technologies 11, no. 5 (2016): 12–20. http://dx.doi.org/10.32362/2410-6593-2016-11-5-12-20.

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This article describes promising technological solutions for the processing, storage and transportation of radioactive waste (RW) implemented by a leading Russian enterprise specializing in the field of radioactive waste management. Federal State Unitary Enterprise "RosRAO" performs nationallevel tasks to ensure nuclear, radiation and environmental safety in the treatment of all types of radioactive waste. To date, FSUE "RosRAO" has a number of ready-made solutions aimed at saving resources while maintaining the radiation and environmental safety by reducing logistics costs due to using large

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Sasaki, Toshiki, Shuji Kaminishi, Yasuaki Miyamoto, and Hideyuki Funasaka. "Research and development activities for cleanup of the Fukushima Daiichi Nuclear Power Station." MRS Proceedings 1518 (2013): 257–68. http://dx.doi.org/10.1557/opl.2013.51.

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ABSTRACTThe Fukushima Daiichi nuclear power station accident and restoration works have produced significant volume of radioactive waste. The waste has very different characteristics from usual radioactive waste produced in nuclear power stations and it requires extensive research and development for management of the waste. R&D works such as analysis of the waste properties, hydrogen generation by radiolysis and diffusion in a storage vessel and corrosion of storage vessels, etc. have been performed for characterization and safe storage of the waste. The detailed R&D plan for processi

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