Relevant bibliographies by topics / Near Surface Disposal Facility

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Academic literature on the topic 'Near Surface Disposal Facility'

Author: Grafiati
Published: 6 September 2023

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Journal articles on the topic "Near Surface Disposal Facility"

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 given disposal facility is evaluated. Different scenarios and assessment cases are developed illustrating the range of possibilities for the evolution and performance of a disposal system without trying to predict its precise behaviour. Within these scenarios, the evolution of the climate will play a major role as the time scales of the evaluation and long term climate evolution overlap. In case of a near-surface facility (Category A waste), ONDRAF/NIRAS is considering the conclusions of the IPCC, demonstrating that a global warming is nearly unavoidable. The consequences of such a global warming and the longer term evolutions on the evolution of the near-surface facility are considered. In case of a geological repository, in which much longer time frames are considered, even larger uncertainties exist in the various climate models. Therefore, the robustness of the geological disposal system towards the possible results of a spectrum of potential climate changes and their time of occurrence will be evaluated. The results of climate modelling and knowledge of past climate changes will merely be used as guidance of the extremes of climate changes to be considered and their consequences.
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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 Nuclear Area. The thickness of the vault in this paper is focused on its ability to withstand radiation from stored waste so that workers or people who are around the disposal facility is safe with maximum radiation dose limit rate of 0.3 μSv / h. The calculation is performed with the aid of MicroShield 7:02 and Rad Pro Calculator Version 3:26 software. From the calculation so that the dose rate at the outer surface of the vault to be 0.3 μSv / h, required walls made of concrete with a density of 2:35 g / cm3 is 62.8 cm thickness.
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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 of concrete to retain radioactive waste within the disposal site is attributed to its high sorption capacity for radionuclides. However, research has shown that the degradation of concrete can affect its radionuclide retention capabilities, which are defined by sorption properties of distribution (Kd) and diffusion (Ds) coefficient parameters. As a result, changes in sorption properties may lead to radionuclides migrating out of the disposal vault. In light of the geochemical deterioration of engineered concrete barriers, this study assesses the long-term safety of near-surface disposal sites. To simulate the impact of concrete degradation on radionuclide migration, we employed RESRAD-OFFSITE’s extended source-term features, which can model the release of radionuclides from radioactive waste shielded by concrete barriers. Using carefully screened published sorption data of four radionuclides (14C, 137Cs, 90Sr and 99Tc) in different stages of concrete degradation, the results indicated that released radioactivity during the most degraded state of concrete will result in a maximum radiation exposure dose of 1.4 × 10−8 mSv/yr from 99Tc which is below the permissible limit of 0.1 mSv per year, thus demonstrating that concrete is a reliable component of the engineered designed barriers for near-surface disposal facilities.
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9

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 protect safety barriers, personnel, the public and the environment. To ensure safety, to prevent the spread of ionizing radiation and radioactive substances from the near-surface disposal facility into the environment, a systematization of safety barriers was carried out to ensure reliable isolation of the placed radioactive waste. Using the experience of building long-term structures, the periods of reliable isolation of the radioactive waste by each of the engineering barriers are indicated. The safety barriers, which are included as the main engineered barriers in the design solutions of the near-surface disposal facilities being created, are consistently considered. Containers are the first engineered barrier. The second barrier is a buffer material based on the natural clays that fills the space between the walls of the modular structures and containers, as well as between the containers themselves. The third barrier is concrete walls, floor slabs and floor slabs of the modular structures of the disposal site. The fourth barrier consists of bentonite mats and a clay castle made of crumpled natural clay. The fifth barrier is a multi-layered covering screen constructed for waterproofing, protection from the atmospheric precipitation, ingress of animals, plant roots and inadvertent human intrusion. The choice of materials for the engineered barriers and the requirements for the characteristics of the barrier are carried out based on the long-term safety assessment calculations, including taking into account the properties of the host rocks.
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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 mobility in the environment and the relatively long half-life in the low-level waste inventory. The scenario considered in the modeling was the normal release to the environment through groundwater. Parameters such as initial radionuclide concentration, soil physical parameters of the study site, and disposal design were entered into AMBER software to be calculated using mathematical formulas. The results show that the radionuclide concentration value in the environment is below the safe limit recommended by the Environmental Supervisory Agency. Likewise, the maximum dose received by the community around the facility is 7.40×10-11 mSv/y, 550 years after the post-closure of the facility, which is also below the regulatory limit of 1 mSv/y for the public.
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