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Journal articles on the topic 'Near Surface Disposal Facility'

Author: Grafiati

Published: 6 September 2023

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1

Nazeeh, K. M., and G. L. Sivakumar Babu. "Reliability analysis of near-surface disposal facility using subset simulation." Environmental Geotechnics 6, no. 4 (2019): 242–49. http://dx.doi.org/10.1680/jenge.17.00004.

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2

Van Geet, M., M. De Craen, D. Mallants, I. Wemaere, L. Wouters, and W. Cool. "How to treat climate evolution in the assessment of the long-term safety of disposal facilities for radioactive waste: examples from Belgium." Climate of the Past Discussions 5, no. 1 (2009): 463–94. http://dx.doi.org/10.5194/cpd-5-463-2009.

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Abstract. In order to protect man and the environment, long-lasting, passive solutions are needed for the different categories of radioactive waste. In Belgium, three main categories of conditioned radioactive waste (termed A, B and C) are defined by radiological and thermal power criteria. It is expected that Category A waste – low and intermediate level short-lived waste – will be disposed in a near-surface facility, whereas Category B and C wastes – high-level and other long-lived radioactive waste – will be disposed in a deep geological repository. In both cases, the long-term safety of a

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3

Cho, Yeseul, Hoseog Dho, Hyungoo Kang, and Chunhyung Cho. "Evaluation of Exposure Dose and Working Hours for Near Surface Disposal Facility." Journal of Nuclear Fuel Cycle and Waste Technology(JNFCWT) 20, no. 4 (2022): 511–21. http://dx.doi.org/10.7733/jnfcwt.2022.039.

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4

Kwon, Mijin, Hyungoo Kang, and Chunhyung Cho. "Study on Rainfall Infiltration Into Vault of Near-surface Disposal Facility Based on Various Disposal Scenarios." Journal of Nuclear Fuel Cycle and Waste Technology(JNFCWT) 19, no. 4 (2021): 503–15. http://dx.doi.org/10.7733/jnfcwt.2021.042.

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5

Sucipta, Sucipta, and Suhartono Suhartono. "DETERMINATION OF CONCRETE VAULT THICKNESS OF NEAR SURFACE DISPOSAL FOR RADIOACTIVE WASTE AT SERPONG NUCLEAR AREA." Jurnal Pengembangan Energi Nuklir 19, no. 2 (2018): 103. http://dx.doi.org/10.17146/jpen.2017.19.2.3624.

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In order to support and complement the radioactive waste management facilities in Indonesia, BATAN will build a demonstration disposal facility in Serpong Nuclear Area (SNA). Demonstration disposal that will be built is Near Surface Disposal (NSD) type. Engineered vault for NSD is reinforced concrete. The calculations for determining the thickness of NSD concrete vault is based on the conceptual design as the result of the placement optimization of demonstration disposal that takes into account the inventory of radioactive waste and environmental geology conditions of the site at Serpong Nucle

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6

Jang, Jiseon, Tae-Man Kim, Chun-Hyung Cho, and Dae Sung Lee. "Radiological Safety Assessment for a Near-Surface Disposal Facility Using RESRAD-ONSITE Code." Journal of Nuclear Fuel Cycle and Waste Technology(JNFCWT) 19, no. 1 (2021): 123–32. http://dx.doi.org/10.7733/jnfcwt.2021.19.1.123.

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7

Capra, B., Y. Billard, W. Wacquier, and R. Gens. "Risk assessment associated to possible concrete degradation of a near surface disposal facility." EPJ Web of Conferences 56 (2013): 05006. http://dx.doi.org/10.1051/epjconf/20135605006.

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8

Mutoni, Agnes, and Juyoul Kim. "Impact of Concrete Degradation on the Long-Term Safety of a Near-Surface Radioactive Waste Disposal Facility in Korea." Applied Sciences 12, no. 18 (2022): 9009. http://dx.doi.org/10.3390/app12189009.

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The migration of radionuclides from radioactive waste into the environment poses a public safety concern. Thus, the long-term safety assessment for near-surface disposal sites for radioactive waste in South Korea entails providing reasonable assurance that the annual radiation dose exposure from radionuclide release from the waste repository into the biosphere will not exceed the regulatory limit of 0.1 mSv/yr. At the first near-surface disposal site in Gyeongju, concrete was a crucial component of the engineered barriers designed to contain radionuclides within the disposal site. The ability

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Kuzmin, E. V., A. V. Minin, M. Yu Bamborin, and Yu V. Trofimova. "System of Engineering Safety Barriers of the Facilities for Near-Surface Disposal of Radioactive Waste." Occupational Safety in Industry, no. 6 (June 2022): 46–51. http://dx.doi.org/10.24000/0409-2961-2022-6-46-51.

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Facilities for near-surface disposal of radioactive waste are very important structures consisting of several safety barriers, and the substantiation and selection of the principal structures of near-surface disposal facility is a complex task that must be solved taking into account the distinctive specifics — the time of their active and passive operation, as well as the period of potential danger of radioactive waste. The paper considers the main approaches to ensuring the long-term safety of near-surface disposal facilities through the use of various engineering safety barriers, measures to

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10

Anggraini, Zeni, Jaka Rachmadetin, Nazhira Shadrina, Sucipta Sucipta, and Heru Sriwahyuni. "Modeling Radiation Exposure from Normal Release of 137Cs Radionuclide to Groundwater for Post-Closure Assessment of Serpong Near Surface Disposal Demo Facility." IOP Conference Series: Earth and Environmental Science 927, no. 1 (2021): 012020. http://dx.doi.org/10.1088/1755-1315/927/1/012020.

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Abstract Near-surface disposal (NSD) has been applied in several countries to dispose of low-level radioactive waste. The demo plant of this disposal type is planned to be constructed in Serpong Nuclear Area, Banten. An assessment of radiation exposure is necessary to ensure the safety requirement of the facility in order to support this program. This study aims to estimate radionuclide migration from the proposed NSD demo facility to the environment and the corresponding total human dose using AMBER mathematical modeling. The representative radionuclide,137Cs, was selected because of its high

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11

Suskin, V. V., I. V. Kapyrin, and F. V. Grigorev. "Assessing the efficiency of a “buried wall” barrier in the establishment of near-surface long-term storage and disposal facilities for RW." Radioactive Waste 14, no. 1 (2021): 96–105. http://dx.doi.org/10.25283/2587-9707-2021-1-96-105.

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The article evaluates the impact of a “buried wall” barrier on the long-term safety during the long-term storage1 or in-situ disposal of nuclear legacy facilities, in particular, industrial reservoirs, as well as during the development of near-surface disposal facilities for radioactive waste (RWDF). For assessment purposes, filtration and mass transfer processes have been numerically modelled in the GeRa code based on a case study of a reference near-surface facility. The study explores in which way the available covering screen affects the dynamics of contaminant spread. It evaluates the sen

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Jakimavičiūtė-Maselienė, Vaidotė, Jonas Mažeika, and Stasys Motiejūnas. "Application of vadose zone approach for prediction of radionuclide transfer from near-surface disposal facility." Progress in Nuclear Energy 88 (April 2016): 53–57. http://dx.doi.org/10.1016/j.pnucene.2015.11.016.

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13

Serebryakov, B. E. "Assessment of the dose to the public from a near-surface radioactive waste disposal facility." Atomic Energy 80, no. 1 (1996): 53–56. http://dx.doi.org/10.1007/bf02415756.

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14

Tokarevsky, O., and I. Iarmosh. "Assessing Impact of Sorption in Geological Medium on Permissible Activity of Radioactive Waste in Near-Surface Disposal Facilities." Nuclear and Radiation Safety, no. 3(75) (August 22, 2017): 34–39. http://dx.doi.org/10.32918/nrs.2017.3(75).06.

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The paper considers the conservative scenario of potential exposure that envisages simultaneous destruction of barriers with simultaneous release of radionuclides by the example of Lot 3 near-surface radioactive waste disposal facility at the Vektor Industrial Complex located in the Chornobyl Exclusion Zone. A conceptual model that considers migration of radionuclides through the aeration zone and aquifer to the potable water well, as well as mixing of infiltration water containing radionuclides with ground water in case of reaching the aquifer, was developed to analyze the mentioned scenario.

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15

Anisimov, N. A., and A. A. Kuvaev. "Numerical Modeling of Moisture Transfer in the Structures of a Near-Surface Radioactive Waste Disposal Facility." Radioactive Waste 20, no. 3 (2022): 97–106. http://dx.doi.org/10.25283/2587-9707-2022-3-97-106.

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The paper considers a model used to calculate the filtration flow in the structural elements of a near-surface radioactive waste disposal facility (RWDF). It presents the results of calculations focused on the filtration and humidity field rates inside the RWDF taking into account changes in the properties of the upper screen, concrete and packages with radioactive waste occurring over time. The study also analyzes the influence of the filtration flow field features on the safety barriers state.

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16

Kim, Hyun-Joo, Minseong Kim, and Jin Beak Park. "Improvement of Safety Approach for Accidents During Operation of LILW Disposal Facility : Application for Operational Safety Assessment of the Near-surface LILW Disposal Facility in Korea." Journal of the Nuclear Fuel Cycle and Waste Technology(JNFCWT) 15, no. 2 (2017): 161–72. http://dx.doi.org/10.7733/jnfcwt.2017.15.2.161.

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17

Yamsani, Sudheer Kumar, Sreedeep Sekharan, and Ravi R. Rakesh. "Combined Shear and Seepage Characteristics for Selecting Drainage Layer in Near Surface Hazardous Waste Disposal Facility." Geotechnical and Geological Engineering 35, no. 2 (2017): 871–78. http://dx.doi.org/10.1007/s10706-016-0135-2.

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18

Setiawan, Budi, and Heru Sriwahyuni. "Determination of 137Cs Elimination from Solution By Tasikmalaya Bentonite and Belitung Quartz Sand As Barrier Material Candidate on the Near Surface Disposal Facility." Jurnal Kimia VALENSI 4, no. 1 (2018): 14–21. http://dx.doi.org/10.15408/jkv.v4i1.7325.

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Batch technique experiment was applied to measure the elimination of 137Cs from solution using bentonite from Tasikmalaya and quartz sand from Belitung. Bentonite material was used as barrier system surrounding on a near surface disposal facility, and quartz sand as backfill material. The distribution coefficient (Kd) of 137Cs on bentonite and quartz sand samples have been measured. Contact time, variation of Na and Cs ion concentrations in solution were applied as the experiment parameters. The Kd values of 137Cs on the samples were 1700 and 3200 ml/g for bentonite and 17 and 37 ml/g for quar

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19

Burne, S., H. S. Wheater, A. P. Butler, et al. "Radionuclide Transport above a Near‐Surface Water Table: I. An Automated Lysimeter Facility for Near‐Surface Contaminant Transport Studies." Journal of Environmental Quality 23, no. 6 (1994): 1318–29. http://dx.doi.org/10.2134/jeq1994.00472425002300060028x.

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20

Gurumoorthy, C. "Experimental methodology to assess migration of iodide ion through Bentonite-Sand Backfill in a Near Surface Disposal Facility." Indian Journal of Science and Technology 5, no. 1 (2012): 1–6. http://dx.doi.org/10.17485/ijst/2012/v5i1.13.

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21

Van Veelen, A., O. Preedy, J. Qi, et al. "Uranium and technetium interactions with wüstite [Fe1–xO] and portlandite [Ca(OH)2] surfaces under geological disposal facility conditions." Mineralogical Magazine 78, no. 5 (2014): 1097–113. http://dx.doi.org/10.1180/minmag.2014.078.5.02.

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AbstractIron oxides resulting from the corrosion of large quantities of steel that are planned to be installed throughout a deep geological disposal facility (GDF) are expected to be one of the key surfaces of interest for controlling radionuclide behaviour under disposal conditions. Over the lengthy timescales associated with a GDF, the system is expected to become anoxic so that reduced Fe(II) phases will dominate. Batch experiments have therefore been completed in order to investigate how a model reduced Fe-oxide surface (wüstite, Fe1–xO) alters as a function of exposure to aqueous solution

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22

Lee, Wang Hyeon, and Jae Hak Cheong. "Potential radiological hazard and options to cope with consequences from recycling of activated metal waste disposed of at a near-surface disposal facility." Annals of Nuclear Energy 152 (March 2021): 107993. http://dx.doi.org/10.1016/j.anucene.2020.107993.

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23

Rao, Sudhakar M., and P. Raghuveer Rao. "Role of the vadose zone in mitigating strontium transport at the near-surface disposal facility (NSDF) in Kalpakkam, India." Bulletin of Engineering Geology and the Environment 75, no. 4 (2015): 1485–91. http://dx.doi.org/10.1007/s10064-015-0772-3.

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24

Arakelyan, A. A., A. I. Blohin, P. A. Blohin, et al. "Refinement of KORIDA software complex and its application in addressing SNF and RW management problems." Radioactive Waste 20, no. 3 (2022): 107–16. http://dx.doi.org/10.25283/2587-9707-2022-3-107-116.

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The paper overviews current progress in the development of the KORIDA software and some examples of its application providing solution to RW and SNF management problems. Its functional capacity has been greatly extended, in particular, providing automated development of models required to calculate exposure doses to personnel based on laser scanning data, as well as through the development of modules evaluating exposure impact on the population and biota. The paper also presents the results of nuclide kinetics module verification and validation, evaluated doses of potential exposure for the po

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25

Walke, R. C., M. C. Thorne, and S. Norris. "Biosphere studies supporting the disposal system safety case in the UK." Mineralogical Magazine 76, no. 8 (2012): 3225–32. http://dx.doi.org/10.1180/minmag.2012.076.8.35.

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AbstractHigher activity radioactive wastes remain hazardous for extremely long timescales, of up to hundreds of thousands of years. Disposing of such wastes deep underground presents the internationally accepted best solution for isolating them from the surface environment on associated timescales. Geological disposal programmes need to assess potential releases from such facilities on long timescales to inform siting and design decisions and to help build confidence that they will provide an adequate degree of safety. Assessments of geological disposal include consideration of the wastes, the

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26

Hong, Sung-Wook, Sangho Park, and Jin Beak Park. "Safety Assessment on the Human Intrusion Scenarios of Near Surface Disposal Facility for Low and Very Low Level Radioactive Waste." Journal of Nuclear Fuel Cycle and Waste Technology 14, no. 1 (2016): 79–90. http://dx.doi.org/10.7733/jnfcwt.2016.14.1.79.

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27

Sujitha, S., Deepthi Mary Dilip, and G. L. Sivakumar Babu. "Time-dependent reliability analysis for radionuclide migration in groundwater in near surface disposal facility using the enhanced Monte Carlo method." Georisk: Assessment and Management of Risk for Engineered Systems and Geohazards 11, no. 2 (2016): 208–14. http://dx.doi.org/10.1080/17499518.2016.1229867.

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28

Hallam, R. J., N. D. M. Evans, and S. L. Jain. "Sorption of Tc(IV) to some geological materials with reference to radioactive waste disposal." Mineralogical Magazine 75, no. 4 (2011): 2439–48. http://dx.doi.org/10.1180/minmag.2011.075.4.2439.

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AbstractOne of the most important isotopes to be considered for disposal in the proposed UK Geological Disposal Facility (GDF) for higher-activity radioactive wastes will be 99Tc, due to its long half-life, high fission yield and ability to migrate through the geosphere as the pertechnetate ion. Much of the Tc is likely to be in the lower Tc(IV) oxidation state due to the low Eh in the near field. Batch Tc(IV) sorption experiments have been performed from pH 3–13, using 95mTc as a spike, in the presence of quartz, hematite, goethite, plagioclase feldspar, sand and shale. Solutions containing T

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29

Dewanto, Pandu, Setyo Sarwanto Moersidik, and Sucipta Sucipta. "Radionuclide Release Prediction in Water and Soil at Demonstration Plant of Near Surface Disposal for Radioactive Waste." Indonesian Journal of Physics and Nuclear Applications 1, no. 2 (2016): 116. http://dx.doi.org/10.24246/ijpna.v1i2.116-122.

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Near Surface Disposal (NSD) for Radioactive Waste that should be developed due to increment of the low level radioactive waste, need to be analyzed and evaluated related to the radiological impact of the environment. A research method applied is done by modeling the distribution of radionuclide releases process. Analysis related with the releases of radionuclide in water and soil is using PRESTO (Prediction of Radiological Effects Due to Shallow Trench Operations). The application scenarios selected in this safety assessment is the migrations of Co-60 and Cs-137 scenario through the shallow gr

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30

Liu, Dong-Xu, Xiao-Wei Xiong, Jin-Sheng Wang, Li-Tang Hu, and Rui Zuo. "Derivation of a speciic activity limit for plutonium for near surface disposal a case study at a potential site in northwest China." Nuclear Technology and Radiation Protection 33, no. 3 (2018): 307–16. http://dx.doi.org/10.2298/ntrp1803307l.

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Based on the safety assessment framework and site-specific characteristic investigations in northwest China, an approach to deriving the specific activity limit of 239Pu is applied to establish a proposed value. Our analyses, in conjunction with the results of other previous studies, allow for the following conclusions: (1) As an intrusion scenario with a feature of minimal site-dependence and pervasive applicability, the drilling scenario can be used as the limiting scenario for the post-closure period; (2) Given a dose limit of 5 mSv per year, a derived specific activity of 287 Bqg-1 (at a d

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31

Hong, Sung-Wook, Jin-Baek Park, and Jung-Hyun Yoon. "Study on the Institutional Control Period Through the Post-drilling Scenario Of Near Surface Disposal Facility for Low and Intermediate-Level Radioactive Waste." Journal of the Nuclear Fuel Cycle and Waste Technology 12, no. 1 (2014): 59–68. http://dx.doi.org/10.7733/jnfcwt.2014.12.1.59.

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32

Baxter, S., D. Holton, S. Williams, and S. Thompson. "Predictions of the wetting of bentonite emplaced in a crystalline rock based on generic site characterization data." Geological Society, London, Special Publications 482, no. 1 (2018): 285–300. http://dx.doi.org/10.1144/sp482.8.

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AbstractA geological disposal facility (GDF) is the widely accepted long-term solution for the management of higher-activity radioactive waste. It consists of an engineered facility constructed in a suitable host rock. The facility is designed to inhibit the release of radioactivity by using a system consisting of engineered and natural barriers. The engineered barriers include the wasteform, used to immobilize the waste, the waste disposal container and any buffer material used to protect the container. The natural barrier includes the rocks in which the facility is constructed. The careful d

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33

Sakib, Khondokar, Abu Haydar, Idris Ali, Debasish Paul, and Shah Alam. "Regional scale screening of selected regions of Bangladesh to identify potential sites for the disposal of low and intermediate level radioactive waste." Nuclear Technology and Radiation Protection 36, no. 1 (2021): 25–37. http://dx.doi.org/10.2298/ntrp210219010s.

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Disposal of radioactive wastes has emerged as a vital issue for Bangladesh as the country is actively working to have a nuclear power plant operating in the country by 2023-2024. The current study aims to find potential sites for a near-surface disposal facility using a geographic information system software and multi-criteria analysis method. Previously six regions (Region-1 to Region-6) were identified upon performing continental scale screening of the whole territory of Bangladesh. In the current study, regional scale screening has been performed of Region-1 and Region-2 using five criteria

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34

Charles, Christopher, Simon Rout, Andrew Laws, Brian Jackson, Sally Boxall, and Paul Humphreys. "The Impact of Biofilms upon Surfaces Relevant to an Intermediate Level Radioactive Waste Geological Disposal Facility under Simulated Near-Field Conditions." Geosciences 7, no. 3 (2017): 57. http://dx.doi.org/10.3390/geosciences7030057.

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35

Kim, Minseong, Sung-Wook Hong, and Jin Beak Park. "Uncertainty Management on Human Intrusion Scenario Assessment of the Near Surface Disposal Facility for Low and Intermediate-Level Radioactive Waste: Comparative Analysis of RESRAD and GENII." Journal of the Nuclear Fuel Cycle and Waste Technology(JNFCWT) 15, no. 4 (2017): 369–80. http://dx.doi.org/10.7733/jnfcwt.2017.15.4.369.

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36

Kwon, Ki Nam, and Jae Hak Cheong. "Development of a reference framework to assess stylized human intrusion scenarios using GENII Version 2 considering design features of planned near-surface disposal facility in Korea." Nuclear Engineering and Technology 51, no. 6 (2019): 1561–74. http://dx.doi.org/10.1016/j.net.2019.04.019.

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37

Shabalin, Borys, Olena Lavrynenko, and Kostiantyn Yaroshenko. "Investigation of the insulating properties of the Cherkasy deposit clays for the creation of underlying screens of radioactive waste at the ‘Vector’ site." Proceedings of the NTUU “Igor Sikorsky KPI”. Series: Chemical engineering, ecology and resource saving, no. 2 (June 28, 2021): 71–81. http://dx.doi.org/10.20535/2617-9741.2.2021.235870.

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The lack of scientifically substantiated requirements, comprehensively developed and approved in a prescribed manner, for the usage of clays as a barrier material poses risks for the safe disposal of radioactive waste in facilities at the ‘Vector’ site for the period of their operation and closure. The bentonite clay from Ukraine’s largest Cherkasy deposit of bentonite and palygorskite clays is considered the most durable as the main component of the insulating (underlying) screens of radioactive waste disposal facilities. The main properties and compositional features of the Cherkasy natural

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Lee, Christopher A., Arjen van Veelen, Katherine Morris, J. Fred W. Mosselmans, Roy A. Wogelius, and Neil A. Burton. "Uranium (VI) Adsorbate Structures on Portlandite [Ca(OH)2] Type Surfaces Determined by Computational Modelling and X-ray Absorption Spectroscopy." Minerals 11, no. 11 (2021): 1241. http://dx.doi.org/10.3390/min11111241.

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Portlandite [Ca(OH)2] is a potentially dominant solid phase in the high pH fluids expected within the cementitious engineered barriers of Geological Disposal Facilities (GDF). This study combined X-ray Absorption Spectroscopy with computational modelling in order to provide atomic-scale data which improves our understanding of how a critically important radionuclide (U) will be adsorbed onto this phase under conditions relevant to a GDF environment. Such data are fundamental for predicting radionuclide mass transfer. Surface coordination chemistry and speciation of uranium with portlandite [Ca

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Leterme, B., D. Mallants, and D. Jacques. "Estimation of future groundwater recharge using climatic analogues and Hydrus-1D." Hydrology and Earth System Sciences Discussions 9, no. 1 (2012): 1389–410. http://dx.doi.org/10.5194/hessd-9-1389-2012.

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Abstract. The impact of climate change on groundwater recharge is simulated using climatic analogue stations, i.e. stations presently under climatic conditions corresponding to a given climate state. The study was conducted in the context of a safety assessment of a future near-surface disposal facility for low and intermediate level short-lived radioactive waste in Belgium; this includes estimating groundwater recharge for the next millennia. Groundwater recharge was simulated using the Richard's based soil water balance model Hydrus-1D and meteorological time series from analogue stations. W

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Shabalin, B. H., К. К. Yaroshenko, and S. P. Buhera. "Peculiarities of 137Cs Sorption/Desorption by Bentonite Clays of Cherkasy Deposit from Groundwater Model Solutions of Radioactive Waste Disposal Facilities at the “Vector” Production Complex." Nuclear Power and the Environment 21, no. 2 (2021): 78–87. http://dx.doi.org/10.31717/2311-8253.21.2.8.

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The main feature of bentonite clays is their high sorption capacity with respect to various radionuclides. The study of sorption kinetics of 137Cs was performed in the static mode by natural and industrial soda modified (PBA-20) samples of bentonite clays of Cherkasy deposit of bentonite and paligorskite clays from groundwater model solutions of radioactive waste disposal facilities of “Vector” production complex under various pH and solution mineralisation. The desorption of occluded samples was studied in distilled water and acetateammonium buffer solution. The value of the degree of sorptio

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Panchal, Y., I. M. Mohamed, Dale Pierce, et al. "An Economic, Technical and Environmental Feasibility Study for Slurry Injection for Biosolids Management in the Dallas Fort Worth Metroplex." Journal of Solid Waste Technology and Management 46, no. 1 (2020): 24–35. http://dx.doi.org/10.5276/jswtm/2020.24.

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In Dallas Fort Worth (DFW), sewage is treated with a combination of anaerobic digestion, effluent filtration and lime stabilization to create biosolids which are then composted, landfilled, or land applied. The current treatment procedure has certain concerns including emissions or accumulation of odors, pathogens, nutrients, metals, and pharmaceutical products.<br/> An alternative method, the Slurry Injection technique, enables the digestion of biosolids in the deep earth and can replace the current practice of wastewater treatment or disposal in a much more environmentally friendly and

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42

Shaikh, Janarul, Sudheer Kumar Yamsani, Sanjeet Sahoo, Sreedeep Sekharan, and Ravi Ranjan Rakesh. "Hydraulic performance assessment of a multi-layered landfill cover system under constant water ponding." Acta Horticulturae et Regiotecturae 25, no. 2 (2022): 129–40. http://dx.doi.org/10.2478/ahr-2022-0017.

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Abstract The engineered multi-layered cover system (MLCS) is used to minimize rainwater infiltration into the wastes accommodated in near surface waste disposal facility (NSDF). It is important to assess the hydraulic performance of MLCS before deploying it in the field. For this purpose, an instrumented three-layered soil column representing MLCS was subjected to 1.5 m constant ponding head for 400 days. The variation of volumetric water content and soil water potential was monitored as a function of depth and time. The objective of the study is to understand the long-term hydraulic performan

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Baston, G. M. N., M. M. Cowper, T. G. Heath, T. A. Marshall, and S. W. Swanton. "The effect of cellulose degradation products on thorium sorption onto hematite: studies of a model ternary system." Mineralogical Magazine 76, no. 8 (2012): 3381–90. http://dx.doi.org/10.1180/minmag.2012.076.8.51.

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AbstractCellulose degradation products (CDPs) can complex with radioelements causing solubility enhancement and sorption reduction, effects which are detrimental to the containment of radionuclides in the near field of a geological disposal facility and surrounding geosphere. Isosaccharinic acid (ISA) is the principal component of CDPs formed under the alkaline anaerobic conditions of a cement-based near field and appears to be largely responsible for the impact of CDPs on radionuclide solubility and sorption under near-field conditions. However, the situation appears to be more complicated un

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Leterme, B., D. Mallants, and D. Jacques. "Sensitivity of groundwater recharge using climatic analogues and HYDRUS-1D." Hydrology and Earth System Sciences 16, no. 8 (2012): 2485–97. http://dx.doi.org/10.5194/hess-16-2485-2012.

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Abstract. The sensitivity of groundwater recharge to different climate conditions was simulated using the approach of climatic analogue stations, i.e. stations presently experiencing climatic conditions corresponding to a possible future climate state. The study was conducted in the context of a safety assessment of a future near-surface disposal facility for low and intermediate level short-lived radioactive waste in Belgium; this includes estimation of groundwater recharge for the next millennia. Groundwater recharge was simulated using the Richards based soil water balance model HYDRUS-1D a

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Bain, Daniel J., Tetiana Cantlay, Brittany Garman, and John F. Stolz. "Oil and gas wastewater as road treatment: radioactive material exposure implications at the residential lot and block scale." Environmental Research Communications 3, no. 11 (2021): 115008. http://dx.doi.org/10.1088/2515-7620/ac35be.

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Abstract The resurgence of oil and gas extraction in the Appalachian Basin has resulted in an excess of oil and gas brines in Pennsylvania, West Virginia, and Ohio. Primarily driven by unconventional development, this expansion has also impacted conventional wells and consequently, created economic pressure to develop effective and cheap disposal options. Using brine as a road treatment, directly or as a processed deicer, however, creates substantial concern that naturally occurring radioactive material in the brines can contaminate roads and road-side areas. Current decision making is based o

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Wissmeier, Laurin, and Joachim Poppei. "Simulating the feedback between corrosive gas generation and water availability for the evaluation of radionuclide mobility in the context of radioactive waste disposal." Safety of Nuclear Waste Disposal 1 (November 10, 2021): 109–10. http://dx.doi.org/10.5194/sand-1-109-2021.

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Abstract. It has been recently recognized that the availability of liquid water may be a controlling factor in the feedback between the physical processes of variably saturated liquid and gas flow on the one hand, and various chemical processes such as metal corrosion in an underground storage facility for radioactive waste on the other hand (e.g., Huang et al., 2021, and reference therein). Iron corrosion in anoxic conditions produces hydrogen gas and consumes water, as expressed by the following stylized chemical equation (e.g., Diercks and Kassner, 1988; Senior et al., 2021): 3Fe+4H2O⟶Fe3O4

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de Visser-Týnová, Eva, Stephen W. Swanton, Stephen J. Williams, Marcel P. Stijkel, Alison J. Walker, and Robert L. Otlet. "14C release from irradiated stainless steel." Radiocarbon 60, no. 6 (2018): 1671–81. http://dx.doi.org/10.1017/rdc.2018.134.

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ABSTRACTRadiocarbon (14C or carbon-14, half-life 5730 yr) is a key radionuclide in the assessment of the safety of a geological disposal facility (GDF) for radioactive waste. In particular, the radiological impact of gaseous carbon-14 bearing species has been recognized as a potential issue. Irradiated steels are one of the main sources of carbon-14 in the United Kingdom’s radioactive waste inventory. However, there is considerable uncertainty about the chemical form(s) in which the carbon-14 will be released. The objective of the work was to measure the rate and speciation of carbon-14 releas

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Hutchinson, D. E., and L. F. Toussaint. "Near-surface disposal of concentrated NORM wastes." Applied Radiation and Isotopes 49, no. 3 (1998): 265–71. http://dx.doi.org/10.1016/s0969-8043(97)00247-9.

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Kim, Ki Beom, Jang Hwa Lee, and Do Gyeum Kim. "Microstructure Analysis on LILW Waste Disposal Facility by Accelerated Steel Corrosion Tests." Applied Mechanics and Materials 378 (August 2013): 194–97. http://dx.doi.org/10.4028/www.scientific.net/amm.378.194.

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Concrete structures such as LILW waste disposal facility located near the sea may suffer from chloride attack damages. This study aims to analysis mock-up test for acceleration corrosion of reinforcing bar and its deterioration in concrete structures by XRD and chloride diffusion coefficient. Corrosion acceleration experiment test has been developed and used to evaluate the effect of corrosion of reinforcing bar caused by seawater on engineered barrier of LILW waste disposal facility.

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Durkee, John. "Managing a Surface Cleaning Facility." Metal Finishing 110, no. 6 (2012): 32–33. http://dx.doi.org/10.1016/s0026-0576(13)70218-6.

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