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Journal articles on the topic 'Nuclear waste'

Author: Grafiati

Published: 4 June 2021

Last updated: 22 June 2024

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1

Rosa, E. A., S. P. Tuler, B. Fischhoff, T. Webler, S. M. Friedman, R. E. Sclove, K. Shrader-Frechette, et al. "Nuclear Waste: Knowledge Waste?" Science 329, no. 5993 (August 12, 2010): 762–63. http://dx.doi.org/10.1126/science.1193205.

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2

Anderson, Kent. "Nuclear Waste." Science 233, no. 4765 (August 15, 1986): 708. http://dx.doi.org/10.1126/science.233.4765.708.a.

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3

Vernier, P. Thomas. "Nuclear Waste." Science 233, no. 4765 (August 15, 1986): 707. http://dx.doi.org/10.1126/science.233.4765.707.c.

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4

Weinberg, Alvin M. "Nuclear Waste." Science 233, no. 4765 (August 15, 1986): 707. http://dx.doi.org/10.1126/science.233.4765.707.b.

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5

Palmer, Ronald A. "Nuclear Waste." Science 233, no. 4765 (August 15, 1986): 707. http://dx.doi.org/10.1126/science.233.4765.707.d.

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6

Wilson, Paul. "Nuclear Waste." Science 233, no. 4765 (August 15, 1986): 707–8. http://dx.doi.org/10.1126/science.233.4765.707.e.

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7

Utter, Donald F. "Nuclear Waste." Science 233, no. 4765 (August 15, 1986): 707. http://dx.doi.org/10.1126/science.233.4765.707.a.

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8

Janata, Jiri, and Roy E. Gephart. "Nuclear Waste." Electrochemical Society Interface 4, no. 4 (December 1, 1995): 46–50. http://dx.doi.org/10.1149/2.f08954if.

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9

JOHNSON, JEFF. "NUCLEAR WASTE." Chemical & Engineering News Archive 82, no. 29 (July 19, 2004): 5. http://dx.doi.org/10.1021/cen-v082n029.p005.

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10

Driscoll, Harry. "Nuclear waste." New Scientist 197, no. 2642 (February 2008): 24–25. http://dx.doi.org/10.1016/s0262-4079(08)60340-1.

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11

UTTER, D. F. "Nuclear Waste." Science 233, no. 4765 (August 15, 1986): 707. http://dx.doi.org/10.1126/science.233.4765.707.

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12

WEINBERG, A. M. "Nuclear Waste." Science 233, no. 4765 (August 15, 1986): 707. http://dx.doi.org/10.1126/science.233.4765.707-a.

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13

VERNIER, P. T. "Nuclear Waste." Science 233, no. 4765 (August 15, 1986): 707. http://dx.doi.org/10.1126/science.233.4765.707-b.

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14

PALMER, R. A. "Nuclear Waste." Science 233, no. 4765 (August 15, 1986): 707. http://dx.doi.org/10.1126/science.233.4765.707-c.

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15

WILSON, P. "Nuclear Waste." Science 233, no. 4765 (August 15, 1986): 707–8. http://dx.doi.org/10.1126/science.233.4765.707-d.

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16

ANDERSON, K. "Nuclear Waste." Science 233, no. 4765 (August 15, 1986): 708. http://dx.doi.org/10.1126/science.233.4765.708.

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17

Harris, Jack. "Nuclear waste." Interdisciplinary Science Reviews 23, no. 3 (September 1998): 187–91. http://dx.doi.org/10.1179/isr.1998.23.3.187.

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18

Desyatov, Denis, Aleksey Ekidin, Konstantin Antonov, and Victor Shatalin. "Waste-specific volume for retrospective, predictive assessments, and ranking of practices during normal operation of Russian nuclear power plants." Nuclear Technology and Radiation Protection 38, no. 2 (2023): 71–79. http://dx.doi.org/10.2298/ntrp2302071d.

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Possibilities of applying the generated radioactive waste-specific volume per unit of produced electricity are shown. This waste specific volume is used for retrospective assessment and forecasting of radio active waste volumes generated at Russian nuclear power plants. According to the available data period covering 2008-2021, the mean and median values of the annual waste-specific volume for each nuclear power plant were obtained. The medians for solid radioactive wastes divided into the categories of very low-level wastes, low-level wastes, intermediate level wastes and high-level wastes are equal to 3.6?10-2, 3.2?10-2, 3.2?10-3, 3.0?10-4 m3(GWh)-1, respectively. For liquid radioactive wastes of the low-level waste and intermediate level waste categories - 1.3?10-3 m3(GWh)-1, 2.4?10-2 m3(GWh)-1, respectively. The highest mean and median values of waste-specific volume for all radioactive waste categories are typical for nuclear power plants with LWGR (RBMK) reactor installations. The forecast based on the plans to increase electricity production by Russian nuclear power plants indicates a likely increase in the volume of radioactive waste generation by 0.7-7.4 % (depending on the waste category) in the period from 2022 to 2027. The waste-specific volume use makes it possible to rank the existing practices of nuclear power plant operation by the volume of radioactive waste generation to justify the criteria for compliance with the International Project on Innovative Nuclear Reactors sustainability methodology.

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19

Liu, Jianquan, and Wentai Dai. "Overview of nuclear waste treatment and management." E3S Web of Conferences 118 (2019): 04037. http://dx.doi.org/10.1051/e3sconf/201911804037.

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Nuclear energy is an efficient energy source. Nuclear fuel has the advantages of high energy density and convenient transportation and storage. After decades of tortuous development, nuclear energy has been well utilized in many ways, especially in the field of nuclear power generation. However, as the number of nuclear power plants continues to increase, the problem of nuclear waste disposal is becoming more and more serious. Nuclear waste disposal is a complex process. For nuclear waste treatment, people initially only temporarily deposit these nuclear wastes or dump them directly. However, as people’s awareness of nuclear waste increases, and the huge potential threat of nuclear waste is known, it is necessary to analyze the current characteristics of nuclear waste and its pollution status in order to find a better nuclear waste treatment and management method.

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20

Weber, William J., Alexandra Navrotsky, Sergey Stefanovsky, Eric R. Vance, and Etienne Vernaz. "Materials Science of High-Level Nuclear Waste Immobilization." MRS Bulletin 34, no. 1 (January 2009): 46–53. http://dx.doi.org/10.1557/mrs2009.12.

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AbstractWith the increasing demand for the development of nuclear power comes the responsibility to address the issue of waste, including the technical challenges of immobilizing high-level nuclear wastes in stable solid forms for interim storage or disposition in geologic repositories. The immobilization of high-level nuclear wastes has been an active area of research and development for over 50 years. Borosilicate glasses and complex ceramic composites have been developed to meet many technical challenges and current needs, although regulatory issues, which vary widely from country to country, have yet to be resolved. Cooperative international programs to develop advanced proliferation-resistant nuclear technologies to close the nuclear fuel cycle and increase the efficiency of nuclear energy production might create new separation waste streams that could demand new concepts and materials for nuclear waste immobilization. This article reviews the current state-of-the-art understanding regarding the materials science of glasses and ceramics for the immobilization of highlevel nuclear waste and excess nuclear materials and discusses approaches to address new waste streams.

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21

Jiang, Zi Ying. "Radioactive Waste Minimization for Nuclear Power Sustainable Development in China." Advanced Materials Research 616-618 (December 2012): 1349–53. http://dx.doi.org/10.4028/www.scientific.net/amr.616-618.1349.

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Radioactive waste minimization is one of the fundamental principles of radioactive waste management, which would reduce the waste volume and activity to the level as low as reasonably achievable. The significance and options of waste minimization methods are reviewed. The nuclear power development and radioactive waste generated in China are summarized. The measures and its function to minimize radioactive wastes and experiences of nuclear power plants (NPPs) in China are analyzed. After Fukushima nuclear accident, China insists on the safety-first principle, reviews its nuclear power development speed. Implementation of waste minimization strategy is an effective and important approach for nuclear power sustainable development.

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22

Xu, George Sikun, and Nicholas Chan. "Management of radioactive waste from application of radioactive materials and small reactors in non-nuclear industries in Canada and the implications for their new application in the future." AIMS Environmental Science 8, no. 6 (2021): 619–40. http://dx.doi.org/10.3934/environsci.2021039.

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<abstract> <p>A large number of artificial-origin radionuclides from irradiation in small reactors and/or nuclear reactions in accelerators are currently used in non-nuclear industries such as education, oil and gas, consumer merchandise, research, and medicine. Radioactive wastes from the use of these radionuclides in non-nuclear industries include expired sealed radioactive sources, biological materials, radionuclide-containing chemicals, contaminated equipment, and very small quantities of used nuclear fuel. Although being less challenging and complex than nuclear energy production and research waste streams, these wastes are subject to the common nuclear regulations by the Canadian Nuclear Safety Commission, and are managed following domestic and international standards and guidelines made by the Canadian Standards Association, International Atomic Energy Agency, and International Organization for Standardization. Management practices used in the nuclear industry in Canada are commonly applied to the non-nuclear industry radioactive waste streams, such as waste handling, treatment, packaging, storage, transportation, clearance and exemptions, and disposal. The half-lives of radionuclides in non‑nuclear applications range from hours to thousands of years, and their activities in non-nuclear industrial applications can be as low as their clearance level or as high as the upper limits for intermediate level radioactive waste. Waste containing only short half-life radionuclides is placed in temporary storage to allow decay, and then is cleared and disposed of through non-radioactive waste routes. Non‑clearable waste materials are treated, consolidated, and managed along with radioactive waste generated from the nuclear industries at designated radioactive waste management sites.</p> </abstract>

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23

Croft, Sally. "Employment: Nuclear waste." Physics World 6, no. 4 (April 1993): 8. http://dx.doi.org/10.1088/2058-7058/6/4/3.

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24

Fang, Hsai-Yang. "Radioactive Nuclear Waste." Practice Periodical of Hazardous, Toxic, and Radioactive Waste Management 6, no. 2 (April 2002): 102–11. http://dx.doi.org/10.1061/(asce)1090-025x(2002)6:2(102).

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25

LEE, T. R., J. BROWN, J. HENDERSON, C. MCDERMID, and H. WHITE. "Nuclear waste management." Nature 317, no. 6038 (October 1985): 570. http://dx.doi.org/10.1038/317570a0.

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26

Fairley, Peter. "Nuclear Waste Land." IEEE Spectrum 44, no. 2 (February 2007): 38–44. http://dx.doi.org/10.1109/mspec.2007.295507.

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27

Gudowski, W. "Nuclear waste management." Nuclear Physics A 752 (April 2005): 623–32. http://dx.doi.org/10.1016/j.nuclphysa.2005.02.133.

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28

Hench, L. L., D. E. Clark, and A. B. Harker. "Nuclear waste solids." Journal of Materials Science 21, no. 5 (May 1986): 1457–78. http://dx.doi.org/10.1007/bf01114698.

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29

Salvatores, M., A. Zaetta, C. Girard, M. Delpech, I. Slessarev, and J. Tommasi. "Nuclear waste transmutation." Applied Radiation and Isotopes 46, no. 6-7 (June 1995): 681–87. http://dx.doi.org/10.1016/0969-8043(95)00133-6.

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30

Latterich, M. "Nuclear waste disposal." Trends in Cell Biology 8, no. 7 (December 1998): 263. http://dx.doi.org/10.1016/s0962-8924(98)01308-7.

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31

Stefanovsky, Sergey V., Sergey V. Yudintsev, Reto Gieré, and Gregory R. Lumpkin. "Nuclear waste forms." Geological Society, London, Special Publications 236, no. 1 (2004): 37–63. http://dx.doi.org/10.1144/gsl.sp.2004.236.01.04.

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32

FORD, JASON. "Britain’s nuclear waste." Engineer 300, no. 7916 (April 2020): 46–47. http://dx.doi.org/10.12968/s0013-7758(22)90402-7.

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33

Leray, S. "Nuclear waste transmutation." Nuclear Instruments and Methods in Physics Research Section B: Beam Interactions with Materials and Atoms 113, no. 1-4 (June 1996): 495–500. http://dx.doi.org/10.1016/0168-583x(95)01402-0.

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34

Ojovan, Michael I. "Nuclear Waste Disposal." Encyclopedia 3, no. 2 (March 30, 2023): 419–29. http://dx.doi.org/10.3390/encyclopedia3020028.

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Nuclear waste (like radioactive waste) is waste that contains, or is contaminated with, radionuclides, at activity concentrations greater than clearance levels set by the regulators, beyond which no further use is foreseen. Disposal is the emplacement of waste in an appropriate facility without the intention to retrieve it.

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35

Flam, Faye. "A Nuclear Cure for Nuclear Waste." Science 252, no. 5013 (June 21, 1991): 1613. http://dx.doi.org/10.1126/science.252.5013.1613.b.

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36

FLAM, F. "A Nuclear Cure for Nuclear Waste." Science 252, no. 5013 (June 21, 1991): 1613. http://dx.doi.org/10.1126/science.252.5013.1613-a.

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37

Robbins, Rebecca A., and Michael I. Ojovan. "Vitreous Materials for Nuclear Waste Immobilisation and IAEA Support Activities." MRS Advances 1, no. 63-64 (2016): 4201–6. http://dx.doi.org/10.1557/adv.2017.209.

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ABSTRACTVitreous materials are the overwhelming world-wide choice for the immobilisation of HLW resulting from nuclear fuel reprocessing due to glass tolerance for the chemical elements found in the waste as well as its inherent stability and durability. Vitrification is a mature technology and has been used for high-level nuclear waste immobilization for more than 50 years. Borosilicate glass is the formulation of choice in most applications although other formulations are also used e.g. phosphate glasses are used to immobilize high level wastes in Russia. The excellent durability of vitrified radioactive waste ensures a high degree of environment protection. Waste vitrification gives high waste volume reduction along with simple and cheap disposal facilities. Although vitrification requires a high initial investment and then operational costs, the overall cost of vitrified radioactive waste is usually lower than alternative options when account is taken of transportation and disposal expenses. Glass has proven to be also a suitable matrix for intermediate and low-level radioactive wastes and is currently used to treat legacy waste in USA, and NPP operational waste in Russia and South Korea. This report is also outlining IAEA activities aiming to support utilisation of vitreous materials for nuclear waste immobilisation.

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38

Jeon, Ji-Hun, Jong-Hwan Lee, Woo-Chun Lee, Sang-Woo Lee, and Soon-Oh Kim. "Solidification of Radioactive Wastes Using Recycled Cement Originating from Decommissioned Nuclear-Energy Facilities." Applied Sciences 14, no. 5 (February 22, 2024): 1781. http://dx.doi.org/10.3390/app14051781.

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Hundreds of thousands of tons of waste are generated from decommissioned nuclear- power facilities, and it has become a critical global issue to secure technology for reducing and recycling this waste. Concrete waste (CW) is estimated to comprise 60–80% of the total waste, and concrete-waste powder (CWP) includes enough inorganic substances used as effective materials for waste treatment. Accordingly, it can be used to produce recycled cement (RC). This study aimed to evaluate the performance of a solidification agent manufactured using recycled cement (SRC) for the safe packing of radioactive wastes, such as coarse aggregates of CW, waste soil, and metal wastes originating from decommissioned nuclear facilities. The experimental results indicated that the most relevant incineration temperature of CWP for RC was 700 °C. The optimum water-to-binder ratio was determined to be 0.4, and the most relevant substitution ratio of ground granulated blast furnace slag for CWP was determined to be 15%. In addition, calcium silicate hydrate is the most effective hydration product for improving the compressive strength of SRC. The maximum packing capacities of the SRC for coarse aggregates, waste soil, and metal waste, which were simulated as radioactive wastes, were determined to be 30, 5, and 7 wt%, respectively. The results of leaching tests using SRC containing radioactive wastes contaminated with Co, Cs, and Sr indicated that their leachability indices met the acceptance level for disposal. Consequently, the RC composed of CWP can be used as a solidifying agent to safely dispose of radioactive wastes, such as coarse aggregates, waste soil, and metal waste.

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39

Tait, J. C., P. J. Hayward, and J. S. Devgun. "Technologies for the containment, immobilization, and disposal of radioactive wastes." Canadian Journal of Civil Engineering 16, no. 4 (August 1, 1989): 444–58. http://dx.doi.org/10.1139/l89-074.

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Atomic Energy of Canada Limited is developing methods for the management and safe disposal of radioactive wastes. These wastes range from the highly radioactive (high-level) UO2 fuel arising from the nuclear generation of electrical power to the low- and intermediate-level wastes arising from research in various Canadian institutions using radioactive isotopes. This paper reviews the current research programs on materials and processes for the immobilization and containment of UO2 fuel wastes and the technical aspects of programs demonstrating the various technologies needed for implementing a disposal program for low-level wastes. Key words: waste management, radioactive, nuclear fuel waste, high-level waste, low-level waste, disposal, immobilization, glass, containment, siting, land burial, geological disposal.

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40

King, S. "A new way for waste [nuclear waste]." Power Engineer 17, no. 6 (2003): 21. http://dx.doi.org/10.1049/pe:20030605.

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41

Vance, Eric R., Dorji T. Chavara, and Daniel J. Gregg. "Progress on Ongoing Waste form HIP projects at ANSTO." MRS Advances 3, no. 20 (2018): 1059–64. http://dx.doi.org/10.1557/adv.2018.328.

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Abstract:Since the year 2000, Synroc has evolved from the titanate full-ceramic waste forms developed in the late 1970s to a hot isostatic pressing (HIP) technology platform that can be applied to produce glass, glass–ceramic, and ceramic waste forms and where there are distinct advantages over vitrification in terms of, for example, waste loading and suppressing volatile losses. This paper describes recent progress on waste form development for intermediate-level wastes from 99Mo production at ANSTO, spent nuclear fuel, fluoride pyroprocessing wastes and 129I. The microstructures and aqueous dissolution results are presented where applicable. This paper provides perspective on Synroc waste forms and recent process technology development in the nuclear waste management industry.

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42

Hunter, Regina L. "Some Materials Concerns in Nuclear Waste Management." MRS Bulletin 17, no. 3 (March 1992): 43–45. http://dx.doi.org/10.1557/s0883769400040847.

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The U.S. Environmental Protection Agency (EPA) has determined that deep geologic disposal is appropriate for three types of radioactive waste generated in the United States: spent fuel, high-level waste, and transuranic waste. Spent fuel is nuclear fuel that has been discharged from a reactor after irradiation. High-level waste (HLW) is the highly radioactive material that remains after the reprocessing of spent fuel to recover uranium or plutonium. Transuranic (TRU) waste is any waste material contaminated with more than 100 nCi/g of elements having atomic numbers greater than 92 and half-lives longer than 20 years. Spent fuel and HLW can result from either commercial or governmental activities, although no commercially generated spent fuel has been reprocessed since 1972. TRU waste results primarily from the design and manufacture of nuclear weapons, not from nuclear power plants.The physical characteristics of TRU waste differ substantially from those of spent fuel and HLW. This imposes different requirements on materials associated with containment and isolation, so TRU waste will be discussed separately from spent fuel and HLW Because all three are judged to be particularly dangerous to human beings and the environment, the EPA standard requires a demonstration of adequate 10,000-year performance of geologic repositories for these radioactive wastes. The U.S. Department of Energy (DOE) is responsible for implementing the standard by designing, siting, and building the repositories.This article briefly describes TRU waste, HLW, and spent fuel and the two repositories currently planned by DOE. It con cludes by offering some observations on materials compatibility among waste, container materials, and host rock.

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43

Stewart, Martin W. A., Eric R. Vance, Sam A. Moricca, Daniel R. Brew, Catherine Cheung, Tina Eddowes, and Walter Bermudez. "Immobilisation of Higher Activity Wastes from Nuclear Reactor Production of99Mo." Science and Technology of Nuclear Installations 2013 (2013): 1–16. http://dx.doi.org/10.1155/2013/926026.

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A variety of intermediate- and low-level liquid and solid wastes are produced from reactor production of99Mo using UAl alloy or UO2targets and in principle can be collectively or individually converted into waste forms. At ANSTO, we have legacy acidic uranyl-nitrate-rich intermediate level waste (ILW) from the latter, and an alkaline liquid ILW, a U-rich filter cake, plus a shorter lived liquid stream that rapidly decays to low-level waste (LLW) standards, from the former. The options considered consist of cementitious products, glasses, glass-ceramics, or ceramics produced by vitrification or hot isostatic pressing for intermediate-level wastes. This paper discusses the progress in waste form development and processing to treat ANSTO’s ILW streams arising from99Mo. The various waste forms and the reason for the process option chosen will be reviewed. We also address the concerns over adapting our chosen process for use in a hot-cell environment.

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44

Ionascu, Laura, Mihaela Nicu, and Felicia Dragolici. "Structural Characterization of Immobilized Waste Forms Containing Secondary Waste from the Liquid Radioactive Waste Treatment." Advanced Materials Research 1151 (March 2019): 35–40. http://dx.doi.org/10.4028/www.scientific.net/amr.1151.35.

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Aqueous liquid radioactive waste is generated during nuclear reactor operations and during industrial and institutional application of radioisotopes. The immobilization of radioactive waste in Portland cement matrix is the most used method, applied in the world by the countries developing nuclear energy programs. The conditioning of the radioactive wastes by cementation process imposes the structural investigation by X-ray diffraction (XRD) of the samples prepared with cement and different ratio of concentrate. This paper gives useful information about the influence of complexing agents related to damages produced in concrete microstructures.

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45

Imada, Takatoshi. "On Nuclear Waste Disposal." Journal of the Atomic Energy Society of Japan 59, no. 5 (2017): 263–67. http://dx.doi.org/10.3327/jaesjb.59.5_263.

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46

Vaughan, Adam. "Nuclear waste in spotlight." New Scientist 254, no. 3389 (June 2022): 7. http://dx.doi.org/10.1016/s0262-4079(22)00948-4.

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47

Alvarez, Robert. "Nuclear Waste: Cleanup curveball." Bulletin of the Atomic Scientists 61, no. 4 (July 1, 2005): 16–18. http://dx.doi.org/10.2968/061004005.

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48

Biggin, Susan. "Nuclear Waste: Hot stuff?" Physics World 7, no. 4 (April 1994): 15. http://dx.doi.org/10.1088/2058-7058/7/4/16.

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49

Lenton, D. "Coming clean [nuclear waste]." IEE Review 49, no. 11 (December 1, 2003): 26–27. http://dx.doi.org/10.1049/ir:20031103.

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50

Cannara, A. "Nuclear Waste: Thorium's Potential." Science 330, no. 6003 (October 21, 2010): 447–48. http://dx.doi.org/10.1126/science.330.6003.447.

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