• Title/Summary/Keyword: Disposal facility

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Deployment of Radioactive Waste Disposal Facility with the Introduction of Nuclear Power Plants (NPP) in Kenya

  • Shadrack, A.;Kim, C.L.
    • Journal of Nuclear Fuel Cycle and Waste Technology
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    • v.1 no.1
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    • pp.37-47
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    • 2013
  • This paper describes basic plans for the development of a radioactive waste disposal facility with the introduction of Nuclear Power Plants (NPPs) for Kenya. The specific objective of this study was to estimate the total projected waste volumes of low- and intermediate-level radioactive waste (LILW) expected to be generated from the Kenyan nuclear power programme. The facility is expected to accommodate LILW to be generated from operation and decommissioning of nuclear power plants for a period of 50 years. An on-site storage capacity of 700 $m^3$ at nuclear power plant sites and a final disposal repository facility of more than 7,000 $m^3$ capacity were derived by considering Korean nuclear power programme radioactive waste generation data, including Kori, Hanbit, and APR 1400 nuclear reactor data. The repository program is best suited to be introduced roughly 10 years after reactor operation. This study is important as an initial implementation of a national LILW disposal program for Kenya and other newcomer countries interested in nuclear power technology.

Site Monitoring and investigation plan for LILW disposal (방사성폐기물 처분장 부지감시 계획)

  • Baek, Seung-Jong
    • Journal of Nuclear Fuel Cycle and Waste Technology(JNFCWT)
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    • v.6 no.4
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    • pp.369-385
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    • 2008
  • The purpose of site monitoring and investigation is to offer the basic data for performance assessment and design of low- and intermediate-level radioactive waste(LILW) disposal facility by monitoring variations of main site properties continually in the stage of pre-operation, operation and post-closure. Main contents of site monitoring are as follows. In the stage of pre-operation, suitability evaluation for disposal facility and monitoring for constructing and operating disposal facility are performed. In the operation period, monitoring is performed including surroundings to research the influence to environment with operating disposal facility and operate safely and efficiently. In the post-closure period, monitoring about major site properties is performed to prevent the effect of radioactive waste from disposal facility and to secure long-term safety.

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The Status and Experiences of LILW Disposal Facility Construction (경주 중·저준위방사성폐기물 처분시설 시공사례 및 현황)

  • Shin, Younglim;Lee, Jongwon
    • Journal of the Korean Society of Mineral and Energy Resources Engineers
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    • v.54 no.4
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    • pp.389-396
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    • 2017
  • This paper presents the status and experiences of Low and Intermediate-level radioactive Waste(LILW) disposal facility in Korea. The LILW disposal facility of 800,000 drums (200 L/drum) is being constructed in the site of KORAD's LILW Disposal Center($206m^2$, Gyeongju-si). The first stage of the LILW facility construction was completed in June 2014, and approved for use by Nuclear Safety and Security Commission (NSSC) in December 2014. The first stage of the LILW facility is a type of underground silo with disposal capacity of $35,200m^3$ (100,000 drums). The second stage of the LILW facility is under construction to be completed by December 2020. Site construction is currently underway. The second stage of the LILW facility is a type of near-surface disposal with disposal capacity of $32,875m^3$ (125,000 drums).

Overview of Finnish Spent Nuclear Fuel Disposal Programme

  • Siren, Topias
    • Journal of the Korean Society of Mineral and Energy Resources Engineers
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    • v.54 no.4
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    • pp.367-376
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    • 2017
  • Finland is the first country in the world constructing the geological spent nuclear fuel disposal facility. The Finnish programme for spent nuclear fuel is organized through a private company Posiva Oy that has been established by the two power companies currently operating nuclear power plants in Finland to dispose owners spent nuclear fuel. First plans for the disposal of the spent nuclear fuel started already at 1978 when first studies for the geological disposal started. The planning was followed by the site selection programme, culminating to the selection of the Olkiluoto site as the disposal site in 2001 by decision in principle by Parlament of Finland. In 2004 the construction of the rock characterization facility ONKALO$^{TM}$ started on the disposal site. ONKALO has served in confirming underground site studies, while it has been designed to be an inseparable part of the final disposal facility. After 10 years of confirming studies in 2015, Posiva Oy, was granted the construction license for the final repository. In early 2020s the disposal of the spent nuclear fuel is expected to start in ONKALO.

Construction and Operational Experiences of Engineered Barrier Test Facility for Near Surface Disposal of LILW (중.저준위 방사성폐기물의 천층처분을 위한 인공방벽 실증시험시설의 건설 및 운전 경험)

  • Jin-Beak Park;Se-Moon Park;Chang-Lak Kim
    • Journal of Nuclear Fuel Cycle and Waste Technology(JNFCWT)
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    • v.2 no.1
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    • pp.23-34
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    • 2004
  • To validate the previous conceptual design of cover system, construction of the engineered barrier test facility is completed and the performance tests of the disposal cover system are conducted. The disposal test facility is composed of the multi-purpose working space, the six test cells and the disposal information space for the PR center. The dedicated detection system measures the water content, the temperature, the matric potential of each cover layer and the accumulated water volume of lateral drainage. Short-term experiments on the disposal cover layer using the artificial rainfall system are implemented. The sand drainage layer shows the satisfactory performance as intended in the design stage. The artificial rainfall does not affect the temperature of cover layers. It is investigated that high water infiltration of the artificial rainfall changes the matric potential in each cover layer. This facility is expected to increase the public information about the national radioactive waste disposal program and the effort for the safety of the planned disposal facility.

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Water Balance Evaluation of Final Closure Cover for Near- surface Radioactive Wastes Disposal Facility

  • Keunmoo Chang;Park, Joo-Wan;Yoon, Jeong-Hyoun;Park, Heui-Joo;Kim, Chang-Lak
    • Nuclear Engineering and Technology
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    • v.32 no.3
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    • pp.274-282
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    • 2000
  • The simulation of water balance was conducted for suggested four alternative multi-layer cover design of near-surface radioactive waste disposal facility under domestic climate condition. The analysis was also conducted for the most favorable one out of four alternative cover design under conservative scenarios. Until 100 years after closure of disposal vault, the infiltration flux for the most favorable cover design was negligible even under doubling of the ambient precipitation condition. When the degradation of asphalt and geomembrane after 100 years of closure was considered, the infiltration flux significantly increased almost to the design criteria of cover system in I' Aube disposal facility. And it was found that the hydraulic conductivity of bentonite/sand as a bottom barrier should be no greater than 1$\times$10$^{-7}$ cm/sec recommended by U.S. EPA.

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Preliminary Post-closure Safety Assessment of Disposal System for Disused Sealed Radioactive Source (폐밀봉선원 처분시스템 예비 폐쇄후 안전성평가)

  • Lee, Seunghee;Kim, Juyoul
    • Journal of Soil and Groundwater Environment
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    • v.22 no.4
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    • pp.33-48
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    • 2017
  • An optimum disposal plan of disused sealed radioactive sources (DSRSs) should be established to ensure long-term disposal safety at the low- and intermediate-level radioactive waste (LILW) disposal facility in Gyeongju. In this study, an optimum disposal system was suggested and preliminary post-closure safety assessment was performed. The DSRSs disposal system was composed of a rock cavern and near surface disposal facilities at the Gyeongju LILW disposal facility. The assessment was conducted using GoldSim program, and probabilistic assessment and sensitivity analysis were implemented to evaluate the uncertainties in the input parameters of natural barriers. Deterministic and probabilistic calculations indicated that the maximum dose was below the regulatory limits ($0.1mSvyr^{-1}$ for the normal scenario, $1mSvyr^{-1}$ for the well scenario). It was concluded that the DSRSs disposal system would maintain environmental safety over a long-time. Moreover, the partition coefficient of Np in host rock, Darcy velocity in host rock, and density of the host rock were the most sensitive parameters in predicting exposure dose in the safety assessment.

Very Low Level Radioactive Solid Waste Management in CHINA (중국에서의 극저준위 방사성 고체 폐기물 관리)

  • Li, Tingjun
    • Journal of Nuclear Fuel Cycle and Waste Technology(JNFCWT)
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    • v.9 no.2
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    • pp.87-92
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    • 2011
  • This paper introduces the policy and regulations on very low level waste (VLLW) management in China. Given the important decommissioning and site restoration program of the old facility, it is considered necessary to create a new disposal facility dedicated to VLLW. Many general design principles are in common with to the disposal facility for low and intermediate level waste (LILW), namely the isolation of the waste by means of a multibarrier system, but using bentonite and/or high density polyethylene membranes instead of the generalized use of concrete barriers. The design of the facility is consistent with the design of disposal facilities for hazardous waste. The engineering design of two VLLW disposal facilities is introduced.

Prediction of Radionuclide Inventory for the Low- and Intermediate-Level Radioactive Waste Disposal Facility by the Radioactive Waste Classification (방사성폐기물 신분류기준을 고려한 중저준위 방사성폐기물 처분시설의 핵종재고량 예측)

  • Jung, Kang Il;Jeong, Noh Gyeom;Moon, Young Pyo;Jeong, Mi Seon;Park, Jin Beak
    • Journal of Nuclear Fuel Cycle and Waste Technology(JNFCWT)
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    • v.14 no.1
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    • pp.63-78
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    • 2016
  • To meet nuclear regulatory requirements, more than 95% individual radionuclides in the low- and intermediate-level radioactive waste inventory have to be identified. In this study, the radionuclide inventory has been estimated by taking the long-term radioactive waste generation, the development plan of disposal facility, and the new radioactive waste classification into account. The state of radioactive waste cumulated from 2014 was analyzed for various radioactive sources and future prospects for predicting the long-term radioactive waste generation. The predicted radionuclide inventory results are expected to contribute to secure the development of waste disposal facility and to deploy the safety case for its long-term safety assessment.

A Case Study on the Safety Assessment for Groundwater Pathway in a Near-Surface Radioactive Waste Disposal Facility

  • Park, Joo-Wan;Chang, Keun-Moo;Kim, Chang-Lak
    • Nuclear Engineering and Technology
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    • v.34 no.3
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    • pp.232-241
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    • 2002
  • A safety assessment is carried out for the near-surface radioactive waste disposal in the reference engineered vault facility. The analysis is mainly divided into two parts. One deals with the release and transport of radionuclide in the vault and unsaturated zone. The other deals with the transport of radionuclide in the saturated zone and radiological impacts to a human group under well drinking water scenario. The parameters for source-term, geosphere and biosphere models are mainly obtained from the site specific data. The results show that the annual effective doses are dominated by long lived, mobile radionuclides and their associated daughters. And it is found that the total effective dose for drinking water is far below the general criteria of regulatory limit for radioactive waste disposal facility.