• 제목/요약/키워드: Decontamination Technology

검색결과 236건 처리시간 0.03초

ABRASIVE BLASTING TECHNOLOGY FOR DECONTAMINATION OF THE INNER SURFACE OF STEAM GENERATOR TUBES

  • Kim, Gye-Nam;Lee, Min-Woo;Park, Hye-Min;Choi, Wang-Kyu;Lee, Kune-Woo
    • Nuclear Engineering and Technology
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    • 제43권5호
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    • pp.469-476
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    • 2011
  • The inner surfaces of bundled inconel tubes from steam generators in South Korean nuclear power plants are contaminated with cobalt and abrasive blasting equipment has been developed to efficiently remove the cobalt. The principal parameters related to the efficient removal using this equipment are the type of abrasive, the distance from the nozzle, and the blasting time. Preliminary tests were performed using oxidized inconel samples which enabled the simulation of cobalt removal from the radioactive inconel samples. The oxygen in the oxidized samples and the cobalt in the radioactive inconel were removed more effectively using the blasting distance, blasting time, and a silicon carbide abrasive. Using the developed abrasive blasting equipment, the optimum decontamination conditions for radioactive inconel samples were blasting for more than 6 minutes using silicon carbides under 5 atmospheric pressures.

원전 해체 시 최적 제염기술 선정을 위한 EXPERT-CHOICE 기법 적용에 대한 연구 (A Study on the Application of EXPERT-CHOICE Technique for Selection of Optimal Decontamination Technology for Nuclear Power Plant of Decommissioning)

  • 송종순;신승수;이상헌
    • 방사성폐기물학회지
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    • 제15권3호
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    • pp.231-237
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    • 2017
  • 본 논문에서는 원전해체 시 적용 가능한 제염기술을 조사하여 분석하였다. 이를 기반으로 최적의 제염기술을 선정하기 위해 의사결정 기법(EXPERT-CHOICE)을 사용하여 기술성을 평가하였다. 이 평가방법은 해당 분야의 전문가로 이루어진 전문가 집단에 의해 수행되는 것이 일반적이다. 가중치를 고려한 결과는 각 기준에 대한 가중치에 평가점수를 곱한 총합을 구하는 식으로 수행하였다. 평가 점수를 3단계로 하여 High, Medium, Low로 구분한 후 가중치를 부여하여 차별화 시킬 수 있다. 하위분류 기준의 세분화와 각 기준 별 가중치의 추가 정량화를 통하여 기술성 분석의 수준을 제고할 수 있고, 좀 더 설득력 있는 결과의 도출을 예상할 수 있다. 평가의 기본 가정은 각 기준 별 가중치를 전문가 조사에 의해 부여하며, 평가 기준은 High에 좀 더 비중을 주는 식으로 차별화 하였다. 이를 반영하면 H, M, L는 대략 "10:5:1"의 비율로 평가 점수를 부여받는데, 이는 EXPERT-CHOICE 기법의 최적화 분석에 따른 것이다. 최고 및 최저값을 제외한 나머지 결과값의 평균을 평가치로 고려하였다.

Electrosorption of U(IV) by Electochemically Modified Activated Carbon Fibers

  • Jung, Chong-Hun;Oh, Won-Zin;Lee, Yu-Ri;Park, Soo-Jin
    • Carbon letters
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    • 제6권1호
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    • pp.25-30
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    • 2005
  • The electrosorption of U(VI) from waste water was carried out by using an activated carbon fiber (ACF) felt electrode in a continuous electrosorption cell. In order to enhance the electrosorption capacity at a lower potential, the ACF was electrochemically modified in an acidic and a basic solution. Pore structure and functional groups of the electrochemically modified ACF were examined, and the effects of the modification conditions were studied for the adsorption of U(VI). Specific surface area of all the ACFs was decreased by this modification. The amount of the acidic functional groups decreased with a basic modification, while the amount increased a lot with an acidic modification. The electrosorption capacity of U(VI) decreased on the acid modified electrode due to the shielding effect of the acidic functional groups. The base modified electrode enhanced the capacity due to a reduction of the acidic functional groups. The electrosorption amount of U(VI) on the base modified electrode at .0.3 V corresponds to that of the as-received ACF electrode at .0.9 V. Such a good adsorption capacity was due to a reduction of the shielding effect and an increase of the hydroxyl ions in the electric double layer on the ACF surface by the application of negative potential.

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고리1호기 계통제염을 위한 원자로냉각재내 유동 특성 평가 (Flow Characteristics Evaluation in Reactor Coolant System for Full System Decontamination of Kori-1 Nuclear Power Plant)

  • 김학수;김초롱
    • 방사성폐기물학회지
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    • 제16권3호
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    • pp.389-396
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    • 2018
  • 국내 가동원전 중 2-루프 가압경수로인 고리1호기는 약 40년 운전한 후, 2017년 6월 18일 영구정지되었다. 영구정지된 고리 1호기는 주요 해체작업을 수행하기전에 계통내 선량률을 저감시켜 작업자피폭을 최소화하기 위한 계통제염을 수행할 예정이다. 일반적으로, 계통제염 범위는 원자로압력용기, 가압기, 증기발생기, 화학 및 체적제어계통, 잔열제거계통 및 원자로 냉각재계통 주요배관을 포함한다. 이러한 계통 및 기기 등을 효율적으로 제염하기 위해서는 제염과정에서 원자로냉각재계통내 유동특성을 평가할 필요가 있다. 계통제염을 위해 순환유량을 제공하는 방법은 다양하나, 본 논문에서는 잔열제거펌프 운전에 따른 고리1호기 원자로냉각재계통내 유동특성을 평가하였다. 잔열제거펌프를 이용한 계통제염은 원자로냉각재 내 유량의 불균형을 초래하여 계통내 기기 및 배관 등에 불순물을 침적시켜 제염이 효율적이지 않다는 것으로 평가되었다.

기체-고체 유동층에서 Chaos 파라메타에 의한 흐름영역의 해석 (Analysis of Flow Regimes by Using Chaos Parameters in Gas-Solid Fluidized Beds)

  • 송평섭;최왕규;정종헌;오원진;강석환;손성모;강용
    • 공업화학
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    • 제17권1호
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    • pp.93-99
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    • 2006
  • 기체-고체 유동층 시스템에서 유동화 흐름영역을 결정할 수 있는 방법들에 대하여 고찰하였다. 기체-고체 시스템의 흐름영역 해석을 위한 상태변수로 상승관내에서의 압력요동을 측정하여 유동화 흐름영역을 해석하였으며, 차압변환기로부터 얻은 압력요동의 자료를 기존의 방법인 평균 및 표준편차를 사용하여 해석하였을 뿐만 아니라, 상관차원이나 Kolmogorov 엔트로피와 같은 chaos 해석 방법을 이용하여 기체-액체 유동층에서 흐름영역을 고찰하였다. 그 결과, 기체-고체 유동층에서 유동화 영역은 평균과 표준편차와 같은 통계적 방법에 의해 결정할 수 있었을 뿐만 아니라, 상관차원과 Kolmogorov 엔트로피와 같은 Chaos 해석방법으로도 유동화영역을 구별할 수 있는 특성으로 사용할 수 있었다.

Effect of Gamma Irradiation and Fumigation on the Biological Qualities of Green, Black, and Oolong Teas

  • Kwon, Joong-Ho;Kausar, Tusneem;Kwon, Yong-Jung;Kim, Jung-Ae;Huh, Eun-Youp;Lee, Kyeong-Yeoll;Saeed, Shafqat
    • Food Science and Biotechnology
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    • 제15권1호
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    • pp.1-4
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    • 2006
  • The biological qualities of green, black, and oolong teas were monitored by observing their microbial decontamination and insect disinfestation following gamma irradiation (0-10 kGy) and fumigation (MeBr or $PH_3$) during 6-month storage at room temperature. Plodia interpunctella Hubner was found as an important quarantine pest in teas used. In a comparative study, both treatments were found to be effective in disinfecting the stored samples. An irradiation dose of 5 kGy was sufficient to control all microorganisms related to the quality of teas, while fumigation with methyl bromide and phosphine showed no appreciable decontamination effect on the microorganisms. As a result, irradiation was found an effective alternative to fumigants for the improvement of biological tea qualities during storage.

고리1호기 해체시 전계통 화학제염 운전개념 (Full System Chemical Decontamination Concept for Kori Unit 1 Decommissioning)

  • 이두호;권혁철;김덕기
    • 방사성폐기물학회지
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    • 제14권3호
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    • pp.289-295
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    • 2016
  • 국내 최초로 건설된 가압경수로형 발전소인 고리1호기는 1978년 4월 첫 상업운전을 개시하였고, 2017년 6월 18일 영구정지 될 계획이다. 고리1호기에서는 사용후핵연료가 사용후핵연료저장조로 모두 이송된 이후, 계통 표면의 선량율을 감소시키기 위한 목적으로 전계통 제염을 실시할 계획이다. 이 논문에서는 해외 원전의 계통제염 사례분석을 통해 국내 최초로 시행될 예정인 고리1호기의 계통제염 운전개념을 기술하고자 하였다.

Decontamination of radioactive wastewater by two-staged chemical precipitation

  • Osmanlioglu, Ahmet E.
    • Nuclear Engineering and Technology
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    • 제50권6호
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    • pp.886-889
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    • 2018
  • This article presented two-staged chemical precipitation for radioactive wastewater decontamination by using chemical agents. The total amount of radioactive wastewater was $35m^3$, and main radionuclides were Cs-137, Cs-134, and Co-60. Initial radioactivity concentration of the liquid waste was 2264, 17, and 9 Bq/L for Cs-137, Cs-134 and Co-60, respectively. Potassium ferrocyanide, nickel nitrate, and ferrum nitrate were selected as chemical agents at high pH levels 8-10 according to the laboratory jar tests. After the process, radioactivity was precipitated as sludge at the bottom of the tank and decontaminated clean liquid was evaluated depending on discharge limits. By this precipitation method decontamination factors were determined as 66.5, 8.6, and 9 for Cs-137, Cs-134, and Co-60, respectively. By using the potassium ferrocyanide, about 98% of the Cs-137 was removed at pH 9. At the bottom of the tank, radioactive sludge amount from both stages was totally $0.98m^3$. It was transferred by sludge pumps to cementation unit for solidification. By chemical processing, 97.2% of volume reduction was achieved. The potassium ferrocyanide in two-staged precipitation method could be used successfully in large-scale applications for removal of Cs-137, Cs-134, and Co-60.

WASHING-ELECTROKINETIC DECONTAMINATION FOR CONCRETE CONTAMINATED WITH COBALT AND CESIUM

  • Kim, Gye-Nam;Yang, Byeong-Il;Choi, Wang-Kyu;Lee, Kune-Woo;Hyeon, Jay-Hyeok
    • Nuclear Engineering and Technology
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    • 제41권8호
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    • pp.1079-1086
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    • 2009
  • A great volume of radioactive concrete is generated during the operation and the decommissioning of nuclear facilities. The washing-electrokinetic technology in this study, which combined an electrokinetic method and a washing method, was developed to decontaminate the concrete generated in nuclear facilities. The results of only an electrokinetic decontamination for the concrete showed that cobalt was removed to below 1% from the concrete due to its high pH. Therefore, the washing-electrokinetic technology was applied to lower the pH of the concrete. Namely, when the concrete was washed with 3 M of hydrochloric acid for 4 hours (0.17 day), the $CaCO_3$ in the concrete was decomposed into $CO_2$ and the pH of the concrete was reduced to 3.7, and the cobalt and cesium in the concrete were removed by up to 85.0% and 76.3% respectively. Next, when the washed concrete was decontaminated by the electrokinetic method with 0.01M of acetic acid in the 1L electrokinetic equipment for 14.83 days, the cobalt and the cesium in the concrete were both removed by up to 99.7% and 99.6% respectively. The removal efficiencies of the cobalt and cesium by 0.01M of acetic acid were increased more than those by 0.05M of acetic acid due to the increase of the concrete zeta potential. The total effluent volume generated from the washing-electrokinetic decontamination was 11.55L (7.2ml/g).

Preliminary analyses on decontamination factors during pool scrubbing with bubble size distributions obtained from EPRI experiments

  • Lee, Yoonhee;Cho, Yong Jin;Ryu, Inchul
    • Nuclear Engineering and Technology
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    • 제53권2호
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    • pp.509-521
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    • 2021
  • In this paper, from a review of the size distribution of the bubbles during pool scrubbing obtained from experiments by EPRI, we apply the bubble size distributions to analyses on the decontamination factors of pool scrubbing via I-COSTA (In-Containment Source Term Analysis). We perform sensitivity studies of the bubble size on the various mechanisms of deposition of aerosol particles in pool scrubbing. We also perform sensitivity studies on the size distributions of the bubbles depending on the diameters at the nozzle exit, the molecular weights of non-condensable gases in the carrier gases, and the steam fractions of the carrier gases. We then perform analyses of LACE-ESPANA experiments and compare the numerical ~ results to those from SPARC-90 and experimental results in order to show the effect of the bubble size distributions.