• Title, Summary, Keyword: Radioactive waste disposal

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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.

WOLSONG LOW- AND INTERMEDIATE-LEVEL RADIOACTIVE WASTE DISPOSAL CENTER: PROGRESS AND CHALLENGES

  • Park, Jin-Beak;Jung, Hae-Ryong;Lee, Eun-Young;Kim, Chang-Lak;Kim, Geon-Young;Kim, Kyung-Su;Koh, Yong-Kwon;Park, Kyung-Woo;Cheong, Jae-Hak;Jeong, Chan-Woo;Choi, Jong-Soo;Kim, Kyung-Deok
    • Nuclear Engineering and Technology
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    • v.41 no.4
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    • pp.477-492
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    • 2009
  • In this paper, we discuss the experiences during the preparation of the Wolsong Low- and Intermediate-Level Radioactive Waste Disposal Center. These experiences have importance as a first implementation for the national LILW disposal facility in the Republic of Korea. As for the progress, it relates to the area of selected disposal site, the disposal site characteristics, waste characteristics of the disposal facility, safety assessment, and licensing process. During these experiences, we also discuss the necessity for new organization and change for a radioactive waste management system. Further effort for the safe management of radioactive waste needs to be pursued.

Review Study of Radioactive Waste Classification and Waste Acceptance Criteria for Disposal of VLLW from Decommissioning of Nuclear Facilities (원자력시설 해체 시 극저준위방사성폐기물 처분을 위한 국내외 방사성폐기물 분류체계 및 인수기준에 대한 연구)

  • Song, Ji Young;Song, Gyo Hyeok;Park, Jin Ho;Ji, Seung Woo;Do, Tae Gwan;Kim, Kwang Pyo
    • Journal of Radiation Industry
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    • v.12 no.3
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    • pp.239-247
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    • 2018
  • Waste acceptance criteria (WAC) for disposal of very low level waste (VLLW), which is generated in large quantities during decommissioning of nuclear facilities should be developed. For the WAC development, it is required to investigate current status to develop WAC for disposal of VLLW. The objective of the present study was to investigate radioactive waste classification and WAC for disposal of VLLW from decommissioning of nuclear facilities. Each country developed its own system for the classification of radioactive waste. Therefore, the classification system for radioactive waste in each country was analyzed to review its WAC of the radioactive waste, which is equivalent to the VLLW in the Korea waste classification system. The category of the VLLW in the waste classification systems of the International Atomic Energy Agency (IAEA) and the United Kingdom (UK) was similar to the category of the VLLW in the waste classification systems of Korea. For the United States(US), the category of Class A was similar to the VLLW in the Korea system. The IAEA provided the general guidance for the WAC based on the safety assessment of disposal system. The US and the UK developed the WAC based on national radioactive waste disposal policy and characteristics of disposal facilities and radioactive waste in addition to the IAEA general guidance. Therefore, the WAC for disposal of VLLW in Korea should be developed by considering the national radioactive waste disposal policy, characteristics of disposal facilities, and the IAEA guidance. This study results will contribute to establishment of national management system of radioactive waste.

Calcium Sulfo Aluminate (CSA) Cement from Coal Ash Utilized as Barriers for Radioactive Waste Disposal

  • Ramakrishna, Chilakala;Thriveni, Thenepalli;Whan, Ahn Ji
    • Journal of Energy Engineering
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    • v.27 no.1
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    • pp.33-39
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    • 2018
  • In this paper, we reviewed briefly about the barrier materials for the radioactive waste disposal. The primary concept of the radioactive waste disposal is safety. The goal of the radioactive waste management is to assure that the environment is not adversely affected and also public. There are a wide variety of materials are available for the radioactive waste disposal or storage. Among those coal fly ash is one of the significant materials are used as a barrier material. Here we reported, the Calcium sulfo aluminate (CSA) from coal fly ash is effectively suitable for the radioactive waste disposal. This is one of the ways of utilization of waste and manufactured the valuable materials for future indeeds.

Prediction of Radionuclide Inventory for Low- and Intermediate-Level Radioactive Waste by Considering Concentration Limit of Waste Package (처분방사능량제한치를 고려한 중저준위 방사성폐기물 처분시설의 핵종재고량 산정(안))

  • Jung, Kang Il;Kim, Min Seong;Jeong, Noh Gyeom;Park, Jin Beak
    • Journal of Nuclear Fuel Cycle and Waste Technology(JNFCWT)
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    • v.15 no.1
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    • pp.65-82
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    • 2017
  • The result of a preliminary safety assessment that was completed by applying the radionuclide inventory calculated on the basis of available data from radioactive waste generation agencies suggested that many difficulties are to be expected with regard to disposal safety and operation. Based on the results of the preliminary safety assessment of the entire disposal system, in this paper, a unit package exceeding the safety goal is selected that occupies a large proportion of radionuclides in intermediate-level radioactive waste. We introduce restrictions on the amount of radioactivity in a way that excludes the high surface dose rate of the package. The radioactivity limit for disposal will be used as the baseline data for establishing the acceptance criteria and the disposal criteria for each disposal facility to meet the safety standards. It is necessary to draw up a comprehensive safety development plan for the Gyeongju waste disposal facility that will contribute to the construction of a Safety Case for the safety optimization of radioactive waste disposal facilities.

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.

Determination of Radionuclide Concentration Limit for Low and Intermediate-level Radioactive Waste Disposal Facility I : Application of IAEA Methodology for Underground Silo Type Disposal Facility (중저준위 방사성폐기물 처분시설의 처분농도제한치 설정에 대한 고찰 I : IAEA 방법론의 동굴처분시설 적용)

  • Hong, Sung-Wook;Kim, Min Seong;Jung, Kang Il;Park, Jin Beak
    • Journal of Nuclear Fuel Cycle and Waste Technology(JNFCWT)
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    • v.15 no.3
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    • pp.257-264
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    • 2017
  • For the safe disposal of intermediate level radioactive waste according to the Nuclear Safety and Security Commission's notice and KORAD's management plan for low and intermediate level radioactive waste, the disposal concentration limit was derived based on the IAEA methodology. The evaluation of the derived disposal concentration limit revealed that it is not suitable as a practical limit for intermediate level radioactive waste. This is because the disposal concentration limit according to the IAEA methodology is derived using a single value of radioactive waste density and the disposal facility's volume. The IAEA methodology is suitable for setting the concentration limit for vault type disposal, which consists of a single type of waste, whereas an underground silo type disposal facility is composed of several types of radioactive waste, and thus the IAEA methodology has limitations in determining the disposal concentration limit. It is necessary to develop and apply an improved method to derive the disposal concentration limit for intermediate level radioactive waste by considering the radioactivity of various types of radioactive waste, the corresponding scenario evaluation results, and the regulatory limit.

Determination of Radionuclide Concentration Limit for Low and Intermediate-Level Radioactive Waste Disposal Facility II: Application of Optimization Methodology for Underground Silo Type Disposal Facility (중저준위방사성폐기물 처분시설의 처분농도제한치 설정에 대한 고찰 II: 최적화 방법론 개발 및 적용)

  • Hong, Sung-Wook;Kim, Min Seong;Jung, Kang Il;Park, Jin Beak
    • Journal of Nuclear Fuel Cycle and Waste Technology(JNFCWT)
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    • v.15 no.3
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    • pp.265-279
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    • 2017
  • The Gyeongju underground silo type disposal facility, approved for use in December 2014, is in operation for the disposal of low and very low-level radioactive wastes, excluding intermediate-level waste. That is why the existing low-level radioactive waste level has been subdivided and the concentration limit value for intermediate-level waste has been changed in accordance with Nuclear Safety Commission Notice 2014-003. For the safe disposal of intermediate-level wastes, new optimization methodology for calculating the concentration limit of intermediate radioactive level wastes at an underground silo type disposal facility was developed. According to the developed optimization methodology, concentration limits of intermediate-level wastes were derived and the inventory of radioactive nuclides was evaluated. The operation and post closure scenarios were evaluated for the derived radioactive nuclide inventory and the results of all scenarios were confirmed to meet the regulatory limit. However, in case of $^{14}C$, it was confirmed that additional radioactivity limitation through a well scenario was needed in addition to the limit of disposal concentration. It was confirmed that the derived intermediate concentration limit of radioactive waste can be used as the intermediate-level waste concentration limit for the underground disposal facility. For the safe disposal of intermediate-level wastes, KORAD plans to acquire additional data from the radioactive waste generator and manage the cumulative radioactivity of $^{14}C$.