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Relevant bibliographies by topics / Near Surface Disposal Facility

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Journal articles

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

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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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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

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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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