• 제목/요약/키워드: radioactive metal

검색결과 289건 처리시간 0.023초

AM, AEM 산화물들의 용융 LiC1에서의 분리 물성 측정 (Measurements of Separation Properties of AM, ARM Oxidesin Molten LiC1)

  • 오승철;박병흥;강대승;서중석;박성원
    • 한국방사성폐기물학회:학술대회논문집
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    • 한국방사성폐기물학회 2003년도 가을 학술논문집
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    • pp.363-367
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    • 2003
  • 우라늄 산화물의 금속전환을 위해 고온 용융염 중에서 전기화학적 환원공정에 대한 관심이 고조되고 있다. 본 공정은 우라늄 산화물뿐만 아니라 다른 악틴족 원소 산화물 및 일부 희토류원소 산화물 역시 금속으로 환원되는 장점을 가지고 있다. 이러한 금속산화물들은 독창적으로 고안된 일체형 음극 및 불활성 양극을 이용하여 금속으로 환원되며, 음극에서 발생된 산소 이온은 양극으로 전달되어 산화됨으로서 산소기체를 발생시킨다. 용융염 중에서 알칼리 및 알칼리토류 산화물에 대한 전기화학적 거동은 아직 완전히 밝혀지지 않았으며, 후행핵연료주기의 단위공정으로서 개발중에 있다. 사용후핵연료의 열 부하는 주로 세슘 및 스트론슘에 의한 것으로, LiC1 용융염 중에서 세슘, 스트론슘 및 바륨 산화물에 대한 용해 속도 및 환원전위를 고찰하였다.

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사용후핵연료 금속겸용용기 인양장비의 구조 안전성 해석 (Structural Safety Analysis of Lifting Device for Spent Fuel Dual-purpose Metal Cask)

  • 문태철;백창열;윤시태;최병일;정인수
    • 방사성폐기물학회지
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    • 제12권4호
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    • pp.299-314
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    • 2014
  • 인양장비는 원자력발전소에서 발생하는 사용후핵연료를 운반하는 운반용기를 인양하기 위해 사용된다. 본 연구는 원자력 안전위원회고시 제2013-27호와 미국 10CFR Part 71 ${\S}71.45$에서 규정하는 기술수준에 따라 이론적인 방법과 유한요소방법으로 인양장비의 구조적안전성을 평가하였다. 이론적으로 평가한 결과 모든 구성 요소에서의 응력이 응력제한치 내에 있어 운영상 발생하는 구조적 안전성을 확보하고 있는 것으로 판단하였다. 또한 유한요소해석을 통한 평가결과, 항복과 극한조건 모두에서 설계기준을 만족하는 것으로 평가되었다. 모든 구성요소에서 충분한 안전여유도(항복조건에서 3 이상의 안전율, 극한조건에서 5 이상의 안전율)를 갖는 것으로 나타나 구조적으로 안전하다고 판단하였다.

황산염환원미생물에 의한 금속재료의 부식 특성 (Corrosive Characteristics of Metal Materials by a Sulfate-reducing Bacterium)

  • 이승엽;정종태
    • 한국광물학회지
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    • 제26권4호
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    • pp.219-228
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    • 2013
  • 방사성 폐기물을 지하에 장기 보관하는 금속 용기에 관한 생지화학적 부식 특성을 알아보기 위해 주철과 구리로 된 금속재료를 환원조건 하에서 디설프리칸스 황산염환원미생물과 3개월간 반응시켰다. 금속재료의 화학적/광물학적 변화를 알아보기 위해 주기적으로 용존 금속이온들의 농도를 측정하였으며, 실험이 종료된 이후 금속 시편 및 표면 이차생성물들을 전자현미경을 이용하여 분석하였다. 디설프리칸스가 없는 조건에서는 금속재료의 부식이 매우 미약하였으나, 미생물이 있는 경우에는 부식이 상대적으로 컸다. 관찰된 생지화학적 부식 산물은 주로 맥키나와이트와 황화구리 같은 검은색의 금속황화물이었으며, 표면에서 쉽게 분리되거나 콜로이드화되어 부유하였다. 특히, 구리 시편의 경우 용액 상에 용존 철이 존재할 때 세균에 의한 구리 부식의 가속화가 관찰되었는데, 이는 구리 표면에 다른 종의 황화철이 성장하면서 구리 간의 결속력을 약화시켰기 때문인 것으로 보인다.

원전 격납건물 라이너플레이트 배면 콘크리트 채움 여부 점검 기술 개발 (Development of Inspection Technique for Filling or Unfilling of Containment Liner Plate Backside Concrete in Nuclear Power Plant)

  • 이정석;김왕배;곽동열
    • 한국압력기기공학회 논문집
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    • 제16권1호
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    • pp.37-41
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    • 2020
  • The Nuclear containment building is a main safety-related structure that performs shielding and conservation functions to prevent highly radioactive materials from leakage to the outside environment in the case of various environmental conditions and postulated accidents. The containment building contains a reactor, steam generator, pressurizer, tank, reactor coolant system, auxiliary system and engineering safety system, and is designed so that highly radioactive materials above the limits specified in 10 CFR 100 do not escape to the outside environment in the case of LOCA(Loss of Coolant Accident) for instance. The containment metal liner plate(CLP) is a carbon steel plate with a nominal plate thickness of 6 mm, which functions as a mold for the wall and dome of the containment building when concrete is filled, fulfills airtightness to prevent leakage of seriously radioactive materials. In recent years, backside corrosion was found on the liner plate in some domestic nuclear power plants. The main cause of backside corrosion was unfilled concrete. In this paper, an inspection technique of assessing filling suitability for CLP backside concrete is developed. Results show that the validity of inspection technique for CLP backside concrete using vibration sensor is successfully verified.

방사성 금속 폐기물의 전해제염 실험 비교 분석 (The Analysis and Comparison of the Experiments for Electro-Decontamination about Radioactive Metal Wastes)

  • 강동우;박광수;문길호;엄달선
    • 한국방사성폐기물학회:학술대회논문집
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    • 한국방사성폐기물학회 2003년도 가을 학술논문집
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    • pp.196-201
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    • 2003
  • 제염이란 방사능에 오염된 물체로부터 방사능을 어느 수준 이하로 떨어뜨리는 모든 종류의 작업을 말한다. 본 논문에서는 제염 방법 중의 한가지인 전해 연마 제염법을 이용한 방사선 오염제거에 대하여 실험을 통하여 기술하였다. 알파선과 베타선에 오염된 각각의 SUS 시편을 사용하여 두 가지 방사선에 대한 제염도를 비교해 보았고, 베타선에 오염된 SUS 및 Carbon steel 시편을 사용한 각 전해액에 대한 제염 실험이 수행되었다. 전해액으로서는 황산, 인산, 질산, 구연산 및 옥살산 등을 사용되었다. 전해액의 종류, 통과하는 전류의 세기 및 시간에 따라 각 시편에 대한 제염도의 차이를 비교, 분석 할 수 있었다.

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영남 지역 대학생들의 식품 위해요인에 대한 위험 지각 특성 연구 (A Study on Risk Perception Characteristics for Food Risk Elements of University Students in Yeungnam Region)

  • 김효정;김미라
    • 동아시아식생활학회지
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    • 제27권4호
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    • pp.450-458
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    • 2017
  • The purpose of this study was to investigate the levels of risk perception characteristics for food risk elements using a psychometric paradigm from 298 university students in Yeungnam region, Korea, by a self-administered questionnaire. The respondents showed the highest level of risk concern about radioactive contaminated foods and the lowest level about GM (genetically modified) foods. In the risk perception characteristics for food risk elements, they perceived radioactive contaminated foods as a catastrophic, worried, new, and uncontrollable risk. In addition, they regarded food additives and foodborne illness as a chronic, controllable, old, and scientifically and individually known risk. According to the results of the factor analysis for risk perception characteristics, dread and unknown were categorized. In the risk perception map, mad cow disease, heavy metal contaminated foods, and radioactive contaminated foods were considered as a dreaded and unknown risk, whereas pesticide residues and GM foods were perceived as a less dreaded and unknown risk. Additionally, food additives and foodborne illness were regarded as a less dreaded and known risk and endocrine disruptors and avian influenza as a dreaded and known risk. These results imply that risk perception characteristics of consumers should be considered to establish strategies for risk communication in food science.

Characterization of Groundwater Colloids From the Granitic KURT Site and Their Roles in Radionuclide Migration

  • Baik, Min-Hoon;Park, Tae-Jin;Cho, Hye-Ryun;Jung, Euo Chang
    • 방사성폐기물학회지
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    • 제20권3호
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    • pp.279-296
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    • 2022
  • The fundamental characteristics of groundwater colloids, such as composition, concentration, size, and stability, were analyzed using granitic groundwater samples taken from the KAERI Underground Research Tunnel (KURT) site by such analytical methods as inductively coupled plasma-mass spectrometry, field emission-transmission electron microscopy, a liquid chromatography-organic carbon detector, and dynamic light scattering technique. The results show that the KURT groundwater colloids are mainly composed of clay minerals, calcite, metal (Fe) oxide, and organic matter. The size and concentration of the groundwater colloids were 10-250 nm and 33-64 ㎍·L-1, respectively. These values are similar to those from other studies performed in granitic groundwater. The groundwater colloids were found to be moderately stable under the groundwater conditions of the KURT site. Consequently, the groundwater colloids in the fractured granite system of the KURT site can form stable radiocolloids and increase the mobility of radionuclides if they associate with radionuclides released from a radioactive waste repository. The results provide basic data for evaluating the effects of groundwater colloids on radionuclide migration in fractured granite rock, which is necessary for the safety assessment of a high-level radioactive waste repository.

Laser decontamination for radioactive contaminated metal surface: A review

  • Qian Wang;Feisen Wang;Chuang Cai;Hui Chen;Fei Ji;Chen Yong;Dasong Liao
    • Nuclear Engineering and Technology
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    • 제55권1호
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    • pp.12-24
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    • 2023
  • With the improvement of laser technology, the strategic needs of efficient and precise decontamination of various components in nuclear application units can be fulfilled by laser decontamination. The surface contaminants of nuclear facilities mainly exist both as loose contaminated layer and fixed oxide layer. The types of radionuclides and contamination layer thickness are closely related to the operation status of nuclear facilities, which have an important influence on the laser decontamination process. This study reviewed the mechanism of laser surface treatment and the influence of laser process parameters on the decontamination thickness, decontamination factor, decontamination efficiency and the distribution of aerosol particle. Although multiple studies have been performed on the mechanism of laser processing and laser decontamination process, there are few studies on the microscopic process mechanism of laser decontamination and the influence of laser decontamination on surface properties. In particular, the interaction between laser and radioactive contaminants needs more research in the future.

Fabrication and Characterization of Zr and Hf Containing Vitrified Forms of Radioactive Waste

  • Young Hwan Hwang;Seong-Sik Shin;Sunghoon Hong;Jung-Kwon Son;Cheon-Woo Kim
    • 방사성폐기물학회지
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    • 제22권2호
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    • pp.173-183
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    • 2024
  • Vitrification, one of the most promising solidification processes for various materials, has been applied to radioactive waste to improve its disposal stability and reduce its volume. Because the thermal decomposition of dry active waste (DAW) significantly reduces its volume, the volume reduction factor of DAW vitrification is high. The KHNP developed the optimal glass composition for the vitrification of DAW. Since vitrification offers a high-volume reduction ratio, it is expected that disposal costs could be greatly reduced by the use of such technology. The DG-2 glass composition was developed to vitrify DAW. During the maintenance of nuclear power plants, metals containing paper, clothes, and wood are generated. ZrO2 and HfO2 are generally considered to be network-formers in borosilicate-based glasses. In this study, a feasibility study of vitrification for DAW that contains metal particulates is conducted to understand the applicability of this process under various conditions. The physicochemical properties are characterized to assess the applicability of candidate glass compositions.

원자로 해체를 위한 수중 아크 금속 절단기술에 대한 연구 (A Study on Contact Arc Metal Cutting for Dismantling of Reactor Pressure Vessel)

  • 김찬규;문도영;문일우;조영태
    • 한국기계가공학회지
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    • 제21권1호
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    • pp.22-27
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    • 2022
  • In accordance with the growing trend of decommissioning nuclear facilities, research on the cutting process is actively proceeding worldwide. In general, a thermal cutting process, such as plasma cutting is applied to decommissioning a nuclear reactor pressure vessel (RPV). Plasma cutting has the advantage of removing the radioactive materials and being able to cut thick materials. However, when operating under water, the molten metal remains in the cut plane and re-solidifies. Hence, cutting is not entirely accomplished. For these environmental reasons, it is difficult to cut thick metal. The contact arc metal cutting (CAMC) process can be used to cut thick metal under water. CAMC is a process that cuts metal using a plate-shaped electrode based on a high-current arc plasma heat source. During the cutting process, high-pressure water is sprayed from the electrode to remove the molten metal, known as rinsing. As the CAMC is conducted without using a shielding gas, such as Argon, the electrode is consumed during the process. In this study, CAMC is introduced as a method for dismantling nuclear vessels and the relationship between the metal removal and electrode consumption is investigated according to the cutting conditions.