• Title/Summary/Keyword: Low-and intermediate-level radioactive waste

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Environmental radiation monitoring program of low- and intermediate- level waste disposal site (중$\cdot$저준위 방사성폐기물 처분시설 환경방사선조사 계획)

  • 윤철환;한재문;김경덕
    • Proceedings of the Korean Radioactive Waste Society Conference
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    • pp.239-243
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    • 2003
  • Environmental monitoring program is investigated based on Atomic Energy Law and foreign country radiation monitoring programs on low-and intermediate level radioactive waste disposal site. It is anticipated that the number of radiation measurements and samples will be higher than those of NPP's. The radiation monitoring program on LLW disposal site should be well prepared reflecting PA, site characteristics and regulation.

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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.

Development of Modified Product Consistency Test

  • Park, Kwansik;Jiawei Sheng;Maeng, Sung-Jun;Song, Myung-Jae
    • Proceedings of the Korean Nuclear Society Conference
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    • pp.391-396
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    • 1998
  • Modified product Consistency Test (M-PCT) has been developed as an alternative to other existing methods in determining the leachability of glass. M-PCT, the leaching method, is a hybrid of MCC-l and PCT, but can provide quicker sample preparation. Larger diameter glass sample (1.0-2.0 mm) than in the PCT method can be used so that the glass beads are more easily produced and cleaned. From the M-PCT, the total mass loss (ML) of glass, the normalized elemental release rate (NLi), pH value of leachate have been obtained. For some selected glasses in which leaching rates have been known, their chemical durablility have been tested using the M-PCT method. The results are compared to the literature data for the glasses. It is found that M-PCT method is reasonable and suitable in determining the leachability of Low and Intermediate level Radioactive Waste glass form, such as the pH, elemental loss and total mass loss.

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The Assessment of Exposure Dose of Radiation Workers for Decommissioning Waste in the Radioactive Waste Inspection Building of Low and Intermediate-Level Radioactive Waste Disposal Facility (경주 중·저준위방사성폐기물 처분시설의 방폐물검사건물에서 해체 방사성폐기물 대상 방사선작업종사자의 피폭선량 평가 및 작업조건 도출)

  • Kim, Rin-Ah;Dho, Ho-Seog;Kim, Tae-Man;Cho, Chun-Hyung
    • Journal of Nuclear Fuel Cycle and Waste Technology(JNFCWT)
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    • v.18 no.2_spc
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    • pp.317-325
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    • 2020
  • The Korea Radioactive Waste Agency plans to expand the storage capacity of radioactive waste by constructing a radioactive waste inspecting building to solve the problem of the lack of inspection space and drum-handling space in the radioactive waste receipt and storage building for the first-stage disposal facility. In this study, the exposure doses of radiation workers that handle new disposal containers for decommissioning waste in the storage areas of the radioactive waste inspecting building were calculated using the Monte Carlo N-particle transport code. The annual collective dose was calculated as a total of 84.8 man-mSv for 304 new disposal containers and an estimated annual 306 working hours for the radiation work. When the 304 new disposal containers (small/medium type) were stored in the storage areas, it was found that 25 radiation workers should be involved in acceptance/disposal inspection, and the estimated exposure dose per worker was calculated as an average annual value of 3.39 mSv. When the radiation workers handle the small containers in high-radiation dose areas, the small containers should be shielded further by increasing the concrete liner thickness to improve the work efficiency and radiation safety of the radiation workers. The results of this study will be useful in establishing the optimal radiation working conditions for radiation workers using the source term and characteristics of decommissioning waste based on actual measurements.

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.

Improvement of Safety Approach for Accidents During Operation of LILW Disposal Facility : Application for Operational Safety Assessment of the Near-surface LILW Disposal Facility in Korea (중·저준위 방사성폐기물 처분시설의 운영 중 사고에 대한 평가체계 개선 : 한국의 중·저준위 방사성폐기물 표층처분시설의 운영 중 안전성평가 적용사례)

  • Kim, Hyun-Joo;Kim, Minseong;Park, Jin Beak
    • Journal of Nuclear Fuel Cycle and Waste Technology(JNFCWT)
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    • v.15 no.2
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    • pp.161-172
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    • 2017
  • To evaluate radiological impact from the operation of a low- and intermediate-level radioactive waste disposal facility, a logical presentation and explanation of expected accidental scenarios is essential to the stakeholders of the disposal facility. The logical assessment platform and procedure, including analysis of the safety function of disposal components, operational hazard analysis, operational risk analysis, and preparedness of remedial measures for operational safety, are improved in this study. In the operational risk analysis, both design measures and management measures are suggested to make it possible to connect among design, operation, and safety assessment within the same assessment platform. For the preparedness of logical assessment procedure, classification logic of an operational accident is suggested based on the probability of occurrence and consequences of assessment results. The improved assessment platform and procedure are applied to an operational accident analysis of the Korean low- and intermediate-level radioactive waste disposal facility and partly presented in this paper.

Concrete Degradation Comparison of Computer Programs for Post-Closure Safety Assessment of Wolsong Low-and Intermediate-Level Radioactive Waste Disposal Facility (월성원자력환경관리센터 폐쇄 후 안전평가 컴퓨터프로그램의 콘크리트 열화현상에 대한 상호비교)

  • Jung, Kang-Il;Bang, Je-Heon;Park, Jin Beak;Yoon, Jeong Hyoun
    • Journal of Nuclear Fuel Cycle and Waste Technology(JNFCWT)
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    • v.11 no.4
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    • pp.311-324
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    • 2013
  • To ensure the reliability of computer programs used for the post-closure safety assessment in the Wolsong LILW Center, the results from MASCOT, SAFE-ROCK and GOLDSIM programs are compared with a problem for degradation. Advantages and disadvantages of each computer programs are individually analyzed. Effects on the individual dose are assessed with each computer programs. MASCOT and SAFE-ROCK showed similar results for $^{129}I$ and $^3H$. However, GOLDSIM represented different results for $^{129}I$ and $^3H$. It is analyzed further and compared with the fluxes in each barrier of the disposal system. Througout the benchmarking testing of the computer program, the limitation of computer program can be continuously found out for the mature post-closure safety of Korean radwaste disposal system.

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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    • 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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Uncertainty Management on Human Intrusion Scenario Assessment of the Near Surface Disposal Facility for Low and Intermediate-Level Radioactive Waste: Comparative Analysis of RESRAD and GENII (중저준위방사성폐기물 표층처분시설의 인간침입 시나리오 평가에 대한 불확실성 관리: RESRAD와 GENII의 비교분석)

  • Kim, Minseong;Hong, Sung-Wook;Park, Jin Beak
    • Journal of Nuclear Fuel Cycle and Waste Technology(JNFCWT)
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    • v.15 no.4
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    • pp.369-380
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    • 2017
  • In order to manage the uncertainty about the evaluation and analysis of the human intrusion scenario of the Gyeongju Low and Intermediate Level Radioactive Waste(LILW) disposal facility, the calculation result by the GENII code was assessed using the RESRAD code, which was developed to evaluate the radiation effects of contaminated soil. The post-drilling scenario was selected as a human intrusion scenario into the near-surface disposal facility to analyze the uncertainty of the modeling by identifying any limitations in the simulation of each code and comparing the evaluation results under the same input data conditions. The results revealed a difference in the migration of some nuclides between the codes, but confirmed that the dose trends at the end of the post-closure control period were similar for all exposure pathways. Based on the results of the dose evaluation predicted by RESRAD, sensitivity analysis on the input factors was performed and major input factors were derived. The uncertainty of the modeling results and the input factors were analyzed and the reliability of the safety evaluation results was confirmed. The results of this study can be applied to the implementation 'Safety Case Program' for the Gyeongju LILW disposal facility.

Comprehensive Development Plans for the Low- and Intermediate-Level Radioactive Waste Disposal Facility in Korea and Preliminary Safety Assessment (우리나라 중·저준위 방사성폐기물 처분시설 종합개발계획(안)과 예비안전성평가)

  • Jung, Kang Il;Kim, Jin Hyeong;Kwon, Mi Jin;Jeong, Mi Seon;Hong, Sung Wook;Park, Jin Beak
    • Journal of Nuclear Fuel Cycle and Waste Technology(JNFCWT)
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    • v.14 no.4
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    • pp.385-410
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    • 2016
  • The disposal facility in Gyeongju is planning to dispose of 800,000 packages of low- and intermediate- level radioactive waste. This facility will be developed as a complex disposal facility that has various types of disposal facilities and accompanying management. In this study, based on the comprehensive development plan of the disposal facility, a preliminary post-closure safety assessment is performed to predict the phase development of the total capacity for the 800,000 packages to be disposed of at the site. The results for each scenario meet the performance target of the disposal facility. The assessment revealed that there is a significant impact of the inventory of intermediate-level radionuclide waste on the safety evaluation. Due to this finding, we introduce a disposal limit value for intermediate-level radioactive waste. With stepwise development of safety case, this development plan will increase the safety of disposal facilities by reducing uncertainties within the future development of the underground silo disposal facilities.