• 제목/요약/키워드: High-level Waste

검색결과 617건 처리시간 0.03초

An Analysis of Constraints on Pyroprocessing Technology Development in ROK Under the US Nonproliferation Policy

  • Jae Soo Ryu
    • 방사성폐기물학회지
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    • 제21권3호
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    • pp.383-395
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    • 2023
  • Since 1997, the Republic of Korea (ROK) has been developing pyro-processing (Pyro) technology to reduce the disposal burden of high-level radioactive waste by recycling spent nuclear fuel (SNF). Compared to plutonium and uranium extraction process, Korean Pyro technology has relatively excellent proliferation resistance that cannot separate pure plutonium owing to its intrinsic characteristics. Regarding Pyro technology development of ROK, the Bush administration considered that Pyro is not reprocessing under the Global Nuclear Energy Partnership, whereas the Obama administration considered that Pyro is subject to reprocessing. However, the Bush and Obama administrations did not allow ROK to conduct full Pyro activities using SNF, even though ROK had faithfully complied with international nonproliferation obligations. This is because the US nuclear nonproliferation policy to prevent the spread of sensitive technologies, such as enrichment and reprocessing, has a strong effect on ROK, unlike Japan, on a bilateral level beyond the NPT regime for non-proliferation of nuclear weapons.

One-pot synthesis of silica-gel-based adsorbent with Schiff base group for the recovery of palladium ions from simulated high-level liquid waste

  • Wu, Hao;Kim, Seong-Yun;Ito, Tatsuya;Miwa, Misako;Matsuyama, Shigeo
    • Nuclear Engineering and Technology
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    • 제54권10호
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    • pp.3641-3649
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    • 2022
  • A simple solvothermal reaction was used to prepare a 3-aminopropyl-functionalized silica-gel-based adsorbent for adsorbing Pd(II) from the nitric acid solution. Scanning electron microscopy, fourier transform infrared spectroscopy, and thermogravimetry analysis were performed on the as-synthesized adsorbent to demonstrate the successful introduction of Schiff base groups. Batch experiments were used to investigate the effects of contact time, nitric acid concentration, solution temperature, and adsorption capacity. It is worth noting that the prepared adsorbent exhibited a higher affinity toward Pd(II) with the uptake approximately 100% even in a 2 M HNO3 solution. At an equilibrium time of 5 h, the maximum adsorption capacity of Pd(II) was estimated to be 0.452 mmol/g. The adsorbed Pd(II) could be completely eluted by dissolving 0.2 M thiourea solution in 0.1 M HNO3. Using a combination of particle-induced X-ray emission analysis and an X-ray photoelectron spectrometer, the adsorbed Pd was found to be uniformly distributed on the surface of the prepared adsorbent and the existing species were Pd(II) and zero-valent Pd(0). Due to the desirable performances, facile preparation method, and abundant raw material source, the prepared adsorbent demonstrated a high application potential in the recovery of Pd(II) from simulated high-level liquid waste treatment.

경주시에 대한 중저준위 방사성폐기물처분장 건설 프로그램의 장기적 효과 (A Long Term Effect Prediction of Radioactive Waste Repository Facility in Gyeongju)

  • 오영민;정창훈
    • 한국시스템다이내믹스연구
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    • 제9권2호
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    • pp.105-128
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    • 2008
  • City of Gyeongju's referendum finally offered the long-waited low-level radioactive waste disposal site in November 2005. Gyeongju's positive decision was due to the various economic rewards and incentives the national government promised to the city. 300 billion won for an accepting bonus, the location of the headquarter building of the Korean Hydro and Nuclear Power Co., and the accelerator research center and 3.25 trillion won for supporting regional development program implementation. All of the above will affect the city's infrastructure and the citizens' economic and social lives. Population, land use, economic structure, SOC and quality of life will be affected. Some will be very positive, and some will be negative. This research project will see the future of the city and forecast the demographic, economic, physical and environmental changes of the city via computer simulation's system dynamics technique. This kind of simulation will help City of Gyeongju's what to prepare for the future. The population forecasting of the year 2046 will be 662,424 with the waste disposal site, and 327,274 without the waste disposal site in Gyeongju. The waste disposal site and regional supporting program will increase 184,246 Jobs more with 1,605 agriculture and fishery, 5,369 manufacturing shops and 27,577 shops. The population increase will bring 96,726 more houses constructed in the city. Land use will also be affected. More land will be developed. And road, water plant and waste water plant will be expanded as much. The city's financial structure will be expanded, due to the increased revenues from the waste disposal site, and property tax revenues from the middle-class employees of the company, and the high-powered scientists and technologists from the accelerator research center. All in all, the future of the city will be brighter after operating the nuclear waste disposal site inside the city.

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난지도 매립지 일대의 지하수위 분포 추정을 위한 복합 크리깅의 응용 (Application of Cokriging for the Estimation of Groundwater Level Distribution at the Nanjido Waste Landfill Area)

  • 정상용;이강근
    • 대한지하수환경학회지
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    • 제2권2호
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    • pp.58-63
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    • 1995
  • 난지도 매립장의 기저침출수위 분포와 그 주변지역의 지하수위 분포를 추정하기 위해 복합크리깅을 이용하였다. 지하수위 분포는 지형의 변화와 밀접한 관련을 갖고 있어서 지형의 변화가 큰 지역에서 지하수위 분포를 추정할 때에는 지형의 표고 자료도 함께 사용하는 것이 더 좋은 결과를 만들어 낸다. 본 연구에서는 87개의 지하수위 자료와 144개의 표고자료에 대한 반베리오그램을 구하고, 그것의 적합한 모델을 교차타당성 조사에 의해 선정한 후 복합크리깅과 정규크리깅을 이용하여 지하수위 분포도 만들었다. 2개의 지하수위 등고선도를 비교해보면 지하수위 자료가 많이 확보된 매립장내에서는 큰 차이가 없으나, 지하수위 표본자료가 부족하고 지형의 변화가 큰 지역(등고선도의 좌상단 구역)과 지하수위 표본자료가 부족한 한강 인접지역에서 끈 차이를 보인다. 이 구역들에서 지형의 표고를 고려해볼 때,복합크리깅에 의한 지하수위 등고선도가 정규크리깅에 의한 지하수위 등고선보다 더 실제에 가까운 것으로 사료된다.

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Swelling Pressures of a Potential Buffer Material for High-Level Waste Repository

  • Lee, Jae-Owan;Cho, Won-Jin;Chun, Kwan-Sik
    • Nuclear Engineering and Technology
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    • 제31권2호
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    • pp.139-150
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    • 1999
  • The swelling pressure of a potential buffer material was measured and the effect of dry density, bentonite content and initial water content on the swelling pressure was investigated to provide the information for the selection of buffer material in a high-level waste repository. Swelling tests were carried out according to Box-Behnken's experimental design. Measured swelling pressures were in the wide range of 0.7 Kg/$\textrm{cm}^2$ to 190.2 Kg/$\textrm{cm}^2$ under given experimental conditions. Based upon the experimental data, a 3-factor polynomial swelling model was suggested to analyze the effect of dry density, bentonite content and initial water content on the swelling pressure The swelling pressure increased with an increase in the dry density and bentonite content, while it decreased with increasing the initial water content and, beyond about 12 wt.% of the initial water content, levelled off to nearly constant value.

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Korean Reference Disposal System for High-level Radioactive Wastes

  • Choi Heui-Joo;Choi Jongwon;Lee Jong Youl
    • 한국방사성폐기물학회:학술대회논문집
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    • 한국방사성폐기물학회 2005년도 Proceedings of The 6th korea-china joint workshop on nuclear waste management
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    • pp.225-235
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    • 2005
  • This paper outlined the status of the development of Korean Reference Disposal (KRS­1) system for high-level radioactive wastes. The repository concept was based on the engineering barrier system which KAERI has developed through a long-term research and development program. The design requirements were prepared for the conceptual design of the repository. The amount of PWR and CANDU spent fuels were projected with the current nuclear power plan. The disposal rates of PWR and CANDU spent fuels were analyzed. The reference geologic characteristics including classification of fracture zones were set for the KRS. The disposal concepts and the layout of the repository were described.

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고준위폐기물 처분터널 내 효율적인 환기시스템에 관한 고찰 (Study on the effective ventilation system in high-level waste disposal tunnel)

  • 윤찬훈;최영철;김진섭
    • 한국소음진동공학회:학술대회논문집
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    • 한국소음진동공학회 2014년도 추계학술대회 논문집
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    • pp.363-364
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    • 2014
  • 국내 에너지의 장기적인 수요상황을 볼 때 원자력 발전의 비중이 확대되는 것은 불가피 하므로 환경 친화적인 사용 후 핵연료의 관리 및 고준위 폐기물의 처분방안의 마련은 원자력의 개발만큼이나 중요하다. 이에 본 연구에서는 방사성 폐기물의 효율적인 관리와 저장 및 열제거를 위하여 최적 환기시스템을 적용한 처분장 설계를 목적으로 여러 환기시스템 설계안을 비교 분석하였다. 분석결과, 8가지 중 case 4(병렬회로)와 case 6(혼합 Diagonal 회로)의 환기효율이 우수한 결과를 나타냈으며, 이와 같은 연구를 통해 환경 친화적인 처분장의 건설이 가능할 것이다.

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Analysis of Functional Criteria for Buffer Material in a High-level Radioactive Waste Repository

  • W. J. Cho;Lee, J. O.;K. S. Chun;Park, Hyun-Soo
    • Nuclear Engineering and Technology
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    • 제31권1호
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    • pp.116-132
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    • 1999
  • This study is intended to analyze the requirements of a buffer material that is one of the major components of the engineered barriers in a high-level radioactive waste repository. The characteristics of potential materials for the buffer in the repository were analyzed and a candidate material was selected. And, based on the current knowledge and the information from various sources, the requirements of a buffer material were evaluated. Finally its quantitative functional criteria on the generic viewpoint has been recommended to be supplied as a guideline for the development of the reference disposal concept and the related buffer material in Korea. The criteria are composed of seven major items, such as hydraulic conductivity, retardation capacity, swelling potential and swelling pressure, thermal conductivity, longevity, organic matter content, and mechanical properties.

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AN ANALYSIS OF THE THERMAL AND MECHANICAL BEHAVIOR OF ENGINEERED BARRIERS IN A HIGH-LEVEL RADIOACTIVE WASTE REPOSITORY

  • Kwon, S.;Cho, W.J.;Lee, J.O.
    • Nuclear Engineering and Technology
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    • 제45권1호
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    • pp.41-52
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    • 2013
  • Adequate design of engineered barriers, including canister, buffer and backfill, is important for the safe disposal of high-level radioactive waste. Three-dimensional computer simulations were carried out under different condition to examine the thermal and mechanical behavior of engineered barriers and rock mass. The research looked at five areas of importance, the effect of the swelling pressure, water content of buffer, density of compacted bentonite, emplacement type and the selection of failure criteria. The results highlighted the need to consider tensile stress in the outer shell of a canister due to thermal expansion of the canister and the swelling pressure from the buffer for a more reliable design of an underground repository system. In addition, an adequate failure criterion should be used for the buffer and backfill.

Three-Dimensional Modelling and Sensitivity Analysis for the Stability Assessment of Deep Underground Repository

  • Kwon, S.;Park, J.H.;Park, J.W.;Kang, C.H.
    • Nuclear Engineering and Technology
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    • 제33권6호
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    • pp.605-618
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    • 2001
  • For the mechanical stability assessment of a deep underground high-level waste repository. computer simulations using FLAC3D were carried out and important parameters including stress ratio, depth, tunnel size, joint spacing, and joint properties were chosen from sensitivity analysis. The main effect as well as the interaction effect between the important parameters could be investigated effectively using fractional factorial design . In order to analyze the stability of the disposal tunnel and deposition hole in a discontinuous rock mass, different modelings were performed under different conditions using 3DEC and the influence of joint distribution and properties, rock properties and stress ratio could be determined. From the three dimensional modelings, it was concluded that the conceptual repository design was mechanically stable even in a discontinuous rock mass.

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