• Title/Summary/Keyword: 중저준위방사성폐기물처분

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Development of Two-Dimensional Near-field Integrated Performance Assessment Model for Near-surface LILW Disposal (중·저준위 방사성폐기물 천층처분시설 근계영역의 2차원 통합성능평가 모델 개발)

  • Bang, Je Heon;Park, Joo-Wan;Jung, Kang Il
    • Journal of Nuclear Fuel Cycle and Waste Technology(JNFCWT)
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    • v.12 no.4
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    • pp.315-334
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    • 2014
  • Wolsong Low- and Intermediate-level radioactive waste (LILW) disposal center has two different types of disposal facilities and interacts with the neighboring Wolsong nuclear power plant. These situations impose a high level of complexity which requires in-depth understanding of phenomena in the safety assessment of the disposal facility. In this context, multidimensional radionuclide transport model and hydraulic performance assessment model should be developed to identify more realistic performance of the complex system and reduce unnecessary conservatism in the conventional performance assessment models developed for the $1^{st}$ stage underground disposal. In addition, the advanced performance assessment model is required to calculate many cases to treat uncertainties or study parameter importance. To fulfill the requirements, this study introduces the development of two-dimensional integrated near-field performance assessment model combining near-field hydraulic performance assessment model and radionuclide transport model for the $2^{nd}$ stage near-surface disposal. The hydraulic and radionuclide transport behaviors were evaluated by PORFLOW and GoldSim. GoldSim radionuclide transport model was verified through benchmark calculations with PORFLOW radionuclide transport model. GoldSim model was shown to be computationally efficient and provided the better understanding of the radionuclide transport behavior than conventional model.

Review and Application of the Radioactive Waste Certification Program (방사성폐기물 인증프로그램의 검토 및 적용)

  • Chung Hee-Jun;Whang Joo-Ho;Lee Jae-Min;Kim Heon;Jeong Yi-Yeong
    • Proceedings of the Korean Radioactive Waste Society Conference
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    • 2005.11a
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    • pp.126-133
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    • 2005
  • Securing of radioactive waste disposal site and the related operations for disposal of low and intermediate level radioactive waste is being actively carried out in Korea. For disposal of radioactive wastes, physicochemical and radiological status and integrity of radioactive wastes must be secured first. Also, waste generators must provide this information to disposers. In addition, to secure the safety of waste disposal, waste acceptance criteria (WAC) and site specific waste acceptance criteria (SWAC) to consider characteristics of the disposal site are required. Radioactive wastes must be processed, generated, managed and transferred in accordance with these criteria. [1] For this, evaluation of properties on each of the radioactive wastes must be performed. However, in reality, atomic power plants are experiencing difficulties in relation to this due to the large quantity of radioactive waste generation. In order to solve this problem, IAEA and major overseas countries have developed, thus are using waste certification program (WCP) and quality assurance program (QAP) [2,3]. On the basis of these programs, radioactive waste certification program has been developed for safe disposal of radioactive wastes in Korea to satisfy the provisions specified in 'low and intermediate level radioactive waste transfer guidelines' of announcement No. 2005-18 from the Ministry of Science and Technology and specific site waste acceptance criteria (tentative plan). In addition, it is being planned to administer amendment on commercial atomic power plant related procedures and ensile staff training in order for early introduction and operation of radioactive waste certification system.

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Radiological Impact Assessment for the Domestic On-road Transportation of Radioactive Isotope Wastes (방사성동위원소 폐기물의 국내육상운반에 관한 방사선영향 평가)

  • Seo, Myunghwan;Hong, Sung-Wook;Park, Jin Beak
    • Journal of Nuclear Fuel Cycle and Waste Technology(JNFCWT)
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    • v.14 no.3
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    • pp.279-287
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    • 2016
  • Korea Radioactive Waste Agency (KORAD) began to operate the low and intermediate level radioactive waste disposal facility in Gyeongju and to transport the radioactive waste containing radioactive isotopes from Daejeon to the disposal facility for the first time at 2015. For this radioactive waste transportation, in this study, radiological impact assessment is carried out for workers and public. The dose rate to workers and public during the transportation is estimated with consideration of the transportation scenarios and is compared with the Korean regulatory limit. The sensitivity analysis is carried out by considering both the variation of release ratios of the radioactive isotopes from the waste and the variation of the distances between the radioactive waste drum and worker during loading and unloading of radioactive waste. As for all the transportation scenarios, radiological impacts for workers and public have met the regulatory limits.

Status of Researches of Excavation Damaged Zone in Foreign Underground Research Laboratories Constructed for Developing High-level Radioactive Waste Disposal Techniques (고준위방사성폐기물 처분 기술개발을 위해 건설된 해외 지하연구시설에서의 암반손상대 연구 현황)

  • Park, Seunghun;Kwon, Sangki
    • Explosives and Blasting
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    • v.35 no.3
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    • pp.31-54
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    • 2017
  • In the countries operating nuclear reactors, the development of high-level radioactive waste(HLW) disposal technique is considered as an urgent and important issue for sustainable utilization of nuclear energy. In Korea, in which a low and intermediate radioactive waste repository is already operating, the construction of an underground research laboratory for in situ validation studies became a matter of interest with increasing concerns on the management of HLW. In order to construct and to operate an underground HLW repository safely in deep underground, the stability of rock mass should be guaranteed. As an important factor on rock stability, excavation damaged zone (EDZ) has been studied in many underground research laboratories in foreign countries. For accurate evaluation of the characteristics and effects of EDZ under disposal condition, it is required to use reliable investigation method based on the analysis of previous studies in similar conditions. In this study, status of foreign underground research laboratories in other countries, approaches for investigation the characteristics, size, and effect of EDZ, and major findings from the researches were surveyed and reported. This will help the accomplishment of domestic researches for developing HLW management techniques in underground research laboratory.

Development of Ground Motion Response Spectrum for Seismic Risk Assessment of Low and Intermediate Level Radioactive Waste Repositories (중·저준위 방사성 폐기물 처분장의 지진위험도 평가를 위한 지반운동스펙트럼 산정)

  • Kim, Min-Kyu;Rhee, Hyun-Me;Lee, Kyoung-Mi
    • Journal of the Earthquake Engineering Society of Korea
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    • v.15 no.1
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    • pp.57-63
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    • 2011
  • In this study, a ground motion response spectrum for the seismic risk assessment of low and intermediate level radioactive waste repositories was developed. For the development of the ground motion response spectrum, a probabilistic seismic hazard analysis (PSHA) was performed. Through the performance of a PSHA, a seismic hazard curve which was based on a seismic bed rock was developed. A uniform hazard spectrum was determined by using a developed seismic hazard curve. Artificial seismic motions were developed based on the uniform hazard spectrum. A seismic response analysis was performed on the developed artificial seismic motion. Finally, an evaluation response spectrum for the seismic risk assessment analysis of low and intermediate level radioactive waste repositories was developed.

Performance Assessment of Engineered Barrier for Retardation of Radionuclide Release in a Low- and Intermediate-Level Radioactive Waste Repository (중저준위방사성폐기물 처분장 인공방벽의 핵종유출 저지능 평가)

  • Cho, W.J.;Lee, J.O.;Hahn, P.S.;Park, H.H.
    • Nuclear Engineering and Technology
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    • v.25 no.3
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    • pp.447-456
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    • 1993
  • A simplified model to assess the performance of engineered barrier for the retardation of radionuclide release in a low- and intermediate-level radioactive waste repository was developed. The model is based on the repository design concept being suggested in Korea, and considers two types of release scenario ; a design-bas release for the design of engineered barrier and a realistic release for the performance assessment. For the numerical illustration, the sample calculations were performed for five radionuclides with different chemical characteristics, and the results were analyzed.

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Logical Analysis for Parameters of Radioactive waste Policy using System Dynamics Technique (시스템 다이내믹스 모델링을 통한 중.저준위방사성폐기물시설 부지선정 영향 인자 분석)

  • Lee, Y.J.;Cho, S.K.
    • Journal of Energy Engineering
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    • v.17 no.2
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    • pp.77-87
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    • 2008
  • Decision-making of the site for the medium and low-level radioactive-waste disposal facilities in 2005 can be estimated as a success. But the limits exposed during the process still remain as problems to be solved. Analyzing the causes of success and failure of the policy and their correlation was expected to provide an effective guideline on future policies. The analysis shows that the transparency of policy makers, the level of community supports and the public relations are decisive factors. System dynamics, a synthetic analyzing tool, is used as a methodology for policy analysis. The result of the system dynamics analysis shows that public confidence is to be the key role to for and against logics when transparency of stakeholder, subsidy and public information are set as adjustable parameters. Public confidence takes a role of leverage that can convert tendency of conclusion by the opinion which influenced by selected parameters.

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.