• Title/Summary/Keyword: disposal

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환경 오염 및 과학 실험실 폐수와 폐기물 처리에 대한 과학 교사들의 인식과 태도 조사 (A Survey of Science Teachers, Perception and Attitudes on Disposal of School Laboratory Waste Water and Materials)

  • 김익희;박국태;정진수
    • 한국환경교육학회지:환경교육
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    • 제20권4호
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    • pp.65-83
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    • 2007
  • The purpose of this study was to survey science teachers, perception and attitudes on disposal of school laboratory waste water and materials. To fulfill this aim, a questionnaire was administered to 244 secondary school science teachers. The result of this study revealed that there was no large disparity in the degree of understanding of laboratory waste disposal and the laboratory waste water treatment, and in secondary science teachers' perception and practicing attitude on the environment. While science teachers had deep understanding of laboratory waste disposal and its influence on environmental pollution, they expressed less positive attitude toward the actual disposal of waste materials and waste water, and participation in teacher training. Therefore, it is necessary to provide standards of systematized disposal methods and proper disposal facilities in middle and high school laboratories, as well as to investigate teachers' needs before providing teacher training program.

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Study on Rainfall Infiltration Into Vault of Near-surface Disposal Facility Based on Various Disposal Scenarios

  • Kwon, Mijin;Kang, Hyungoo;Cho, Chunhyung
    • 방사성폐기물학회지
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    • 제19권4호
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    • pp.503-515
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    • 2021
  • In this study, rainfall infiltration in vault of the second near-surface disposal facility was evaluated on the basis of various disposal scenarios. A total of four different disposal scenarios were examined based on the locations of the radioactive waste containers. A numerical model was developed using the FEFLOW software and finite element method to simulate the behavior of infiltrated water in each disposal scenario. The effects of the disposal scenarios on the infiltrated water were evaluated by estimating the flux of the infiltrated water at the vault interfaces. For 300 years, the flux of infiltrated water flowing into the vault was estimated to be 1 mm/year or less for all scenario. The overall results suggest that when the engineered barriers are intact, the flux of infiltrated water cannot generate a sufficient pressure head to penetrate the vault. In addition, it is confirmed that the disposal scenarios have insignificant effects on the infiltrated water flowing into the vault.

A Study on Thermal Load Management in a Deep Geological Repository for Efficient Disposal of High Level Radioactive Waste

  • Jongyoul Lee;Heuijoo Choi;Dongkeun Cho
    • 방사성폐기물학회지
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    • 제20권4호
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    • pp.469-488
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    • 2022
  • Technology for high-level-waste disposal employing a multibarrier concept using engineered and natural barrier in stable bedrock at 300-1,000 m depth is being commercialized as a safe, long-term isolation method for high-level waste, including spent nuclear fuel. Managing heat generated from waste is important for improving disposal efficiency; thus, research on efficient heat management is required. In this study, thermal management methods to maximize disposal efficiency in terms of the disposal area required were developed. They efficiently use the land in an environment, such as Korea, where the land area is small and the amount of waste is large. The thermal effects of engineered barriers and natural barriers in a high-level waste disposal repository were analyzed. The research status of thermal management for the main bedrocks of the repository, such as crystalline, clay, salt, and other rocks, were reviewed. Based on a characteristics analysis of various heat management approaches, the spent nuclear fuel cooling time, buffer bentonite thermal conductivity, and disposal container size were chosen as efficient heat management methods applicable in Korea. For each method, thermal analyses of the disposal repository were performed. Based on the results, the disposal efficiency was evaluated preliminarily. Necessary future research is suggested.

수평 터널방식 고준위폐기물 처분시스템 주변 열 해석 (Thermal Analysis of a Horizontal Disposal System for High-level Radioactive Waste)

  • 최희주;김인영;이종열;김현아
    • 터널과지하공간
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    • 제23권2호
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    • pp.141-149
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    • 2013
  • 경수로 사용 후 핵연료의 파이로 공정 처리를 통해 예상되는 고준위폐기물 처분시스템을 대상으로 열적 성능평가를 수행하였다. 처분방식으로 수평 처분터널 처분시스템을 고려하였다. 수평 처분터널 간격 25 미터와 처분공 간격 2미터를 대상으로 평가하였다. 세라믹폐기물 수평 처분터널 주변의 다양한 위치에 대해 장기간 동안 열 해석을 통하여 온도 변화를 해석하였다. 열 해석은 ABAQUS 프로그램을 이용하였다. 열 해석 결과에 의하면 처분시스템 중 어느 부분에서도 최고 온도가 $100^{\circ}$를 넘지 않아, 열적 성능 기준을 만족하였다. 열 해석 결과에 따르면, 처분시스템 중앙에 위치한 처분용기 주변이 외곽에 위치한 것의 주변보다 최고 온도 기준으로 약 $3^{\circ}$정도 높았다. 이것은 처분시스템 설계시 가능한 외곽에 위치한 처분용기가 많도록 설계하는 것이 처분밀도를 향상시킬 수 있음을 시사하였다.

사용후핵연료봉 밀집을 고려한 심지층처분 개념 분석 (An Analysis of the Deep Geological Disposal Concepts Considering Spent Fuel Rods Consolidation)

  • 이종열;김현아;이민수;김건영;최희주
    • 방사성폐기물학회지
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    • 제12권4호
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    • pp.287-297
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    • 2014
  • 사용후핵연료 또는 고준위폐기물의 안전한 처분을 위하여 지난 수십 년 동안 많은 나라들이 다양한 처분대안을 연구하여 왔다. 본 논문에서는 심지층처분기술에 있어서 사용후핵연료를 직접 처분하는 방안으로서 처분효율 향상을 위한 다양한 방안 중의 하나로 고려할 수 있는 PWR 사용후핵연료 집합체를 해체하여 연료봉을 밀집한 경우에 대한 처분 효율을 분석하였다. 이를 위하여, 우선 사용후핵연료 연료봉 밀집개념과 관련 처분용기 및 심지층처분 개념을 설정하였다. 이 개념에 근거하여 심지층 처분시스템의 공학적방벽 설계에 있어서 가장 중요한 요건인 완충재의 온도 제한요건을 만족시키는지 여부를 확인하기 위하여 각 처분개념 별로 열해석을 수행하였다. 그리고, 처분공 간격, 처분터널 간격 및 처분용기 열발산 면적에 따른 열해석 결과를 바탕으로, 단위처분면적 관점에서의 처분효율을 비교/분석하고 평가하였다. 또한, 사용후핵연료봉을 밀집시킨 경우에 있어서 냉각기간에 따른 처분개념을 분석하였다. 분석결과에 따르면 사용후핵연료봉을 밀집하여 심지층처분하는 경우 처분효율 측면에서 불리한 것으로 판단되었다. 다만, 사용후핵연료의 냉각기간을 70년 이상으로 장기화 할 경우 처분효율은 향상될 것으로 예상되지만, 사용후핵연료의 내구성 및 장기저장에 따른 조건 등 추가적인 분석이 필요하다.

대학생들의 의복 처분 결정요인에 대한 분석 (An Analysis on College Students′ Clothing Disposal Determinants)

  • 홍연숙
    • 복식문화연구
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    • 제6권2호
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    • pp.92-108
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    • 1998
  • The purpose of this study was designed a) to examine the relative importance for college students' clothing disposal causes and their factor structure: b) to test the effects of gender, clothing satisfaction and family income on clothing disposal determinants; and c) to assess the relationship between clothing purchase determinants and overall clothing satisfaction and clothing disposal determinants. Data (n=660) were collected from college students in Cheju Do. The survey questionnaire composed of a revised Clothing Disposal Determinants Scale, Clothing Purchase Determinants Scale and background variables. First, the most important reasons for clothing disposal were to unfit with body change, get washed our and raise nap on clothe, wornout with long-term use, do not ware for new purchasing clothe, uneasy on wear. Second, factor analysis of the revised Clothing Disposal Determinants Scale revealed five factors; unfitness, fashion change, quality dissatisfaction, product efficiency decrement, and maintenance/inconvenience. Third, female students perceived significantly higher in fashion change and unfitness than male students. Forth, unfitness and product efficiency decrement were significantly discriminated between between clothing satisfaction groups, unfitness and fashion change variables were significantly discriminated between family income groups. fifth, impulsive purchase factor was the best predictor of composite clothing disposal measure, followed by individuality, clothing satisfaction, practicality. The best predictors of each disposal factors were individuality oriented purchasing criterion in unfitness factor. Fashion in fashion change, impulsive purchase in quality dissatisfaction and product efficiency decrement factors, and practicality in maintenance/inconvenience factor. As a whole, the most consistent predictor of clothing disposal determinants was impulsive purchase factor.

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Current Status of Nuclear Waste Management (and Disposal) in the United States

  • McMahon, K.;Swift, P.;Nutt, M.;Birkholzer, J.;Boyle, W.;Gunter, T.;Larson, N.;MacKinnon, R.;Sorenson, K.
    • Journal of Nuclear Fuel Cycle and Waste Technology
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    • 제1권1호
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    • pp.29-35
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    • 2013
  • The United States Department of Energy (US DOE) is conducting research and development (R&D) activities under the Used Fuel Disposition Campaign (UFDC) to support storage, transportation, and disposal of used nuclear fuel (UNF) and wastes generated by existing and future nuclear fuel cycles. R&D activities are ongoing at nine national laboratories, and are divided into storage, transportation and disposal. Storage R&D focuses on closing technical gaps related to extended storage of UNF. Transportation R&D focuses on ensuring transportability of UNF following extended storage, and addressing data gaps regarding nuclear fuel integrity, retrievability, and demonstration of subcriticality. Disposal R&D focuses on identifying geologic disposal options and addressing technical challenges for generic disposal concepts in mined repositories in salt, clay/shale, and granitic rocks, and deep borehole disposal. UFDC R&D goals include increasing confidence in the robustness of generic disposal concepts, reducing generic sources of uncertainty that may impact the viability of disposal concepts, and developing science and engineering tools to support the selection, characterization, and licensing of a repository. The US DOE has also initiated activities in the Nuclear Fuel Storage and Transportation (NFST) Planning Project to facilitate the development of an interim storage facility and to support transportation infrastructure in the near term.

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

  • 이승희;김주열
    • 한국지하수토양환경학회지:지하수토양환경
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    • 제22권4호
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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.

처분효율 향상을 위한 CANDU 사용후핵연료 처분개념 도출 (Development of CANDU Spent Fuel Disposal Concepts for the Improvement of Disposal Efficiency)

  • 이종열;조동건;국동학;이민수;최희주;이양
    • 방사성폐기물학회지
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    • 제7권4호
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    • pp.229-236
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    • 2009
  • 우리나라에서 발생하는 사용후핵 연료를 CANDU형과 PWR형 2종류로 구분한다. PWR형 사용후핵 연료의 경우 적절한 공정을 거쳐 원료물질로 다시 사용할 수 있는 물질을 많이 포함하고 있어 재활용 공정을 고려할 수 있다. CANDU형 사용후핵 연료는 천연 우라늄을 원료물질로 사용하고 있어 재활용 가능성이 거의 없으므로 직접 처분을 고려하고 있다. 본 논문에서는 PWR형과 CANDU형 사용후핵연료 모두를 직접 처분하는 개념으로 개발한 한국형 사용후핵연료 처분시스템을 바탕으로 CANDU형 사용후핵연료 처분 시스템을 향상시키는 방안을 도출하고자 하였다. 이를 위하여, 현재 원자력발전소에서 사용하고 있는 사용후핵연료 60 다발(Bundle) 용량의 저장바스켓을 포장 활용하는 방안으로 처분용기 개념을 개선하였다. 이들 개선한 처분용기를 기반으로 하여 사용후핵연료의 심지층 처분시스템에 있어서 주요한 제한요건인 폐기물로부터 발생된 열로 인하여 완충재의 온도가 $100^{\circ}C$를 넘지 않도록 하는 요건을 만족시키면서 효율을 향상시킨 처분시스템 개념을 제시하였다. 제시한 처분 시스템 개념들은 장기저장 및 회수성이 용이한 방안을 도입한 개념과 개선한 처분용기를 1개 처분공에 2단으로 처분하는 것으로서 이들 개념을 기존 한국형 처분시스템과 효율성 측면 에서 비교 분석하였다. 본 연구를 통하여 얻은 CANDU 사용후핵연료 처분개념은 단위면적당 열효율, U-density, 처분면적, 굴착량, 완충재 및 폐쇄 물질량을 30~40 %까지 효율을 향상시킬 수 있었다.

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