• Title/Summary/Keyword: radioactive metal

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

  • 오승철;박병흥;강대승;서중석;박성원
    • Proceedings of the Korean Radioactive Waste Society Conference
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    • 2003.11a
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    • pp.363-367
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    • 2003
  • Much attention has been given to an electrochemical reduction process for converting uranium oxide to uranium metal in molten salt. The process has the versatility of being adopted for reducing other actinide and rare-earth metals from their oxides. Using the metal oxide to be reduced as a integrated cathode designed originally and inert conductors as anodes, oxygen anions are removed from the cathode and oxidized at the surface of the anodes in a molten salt cell. However, the electrochemical properties of alkali and alkali-earth metal oxides in molten salt have not been investigated thoroughly, which made the process incomplete when it is considered as a unit process in a back-end fuel cycle. It is well known that cesium and strontium Isotopes in spent fuel are main contributors for head load. The properties of cesium, strontium, and barium oxides such as the dissolution rates and reduction potentials in molten LiC1 dissolving $Li_2O$ are examined.

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

  • Moon, Tae-Chul;Baeg, Chang-Yeal;Yun, Si-Tae;Choi, Byung-Il;Jung, In-Su
    • Journal of Nuclear Fuel Cycle and Waste Technology(JNFCWT)
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    • v.12 no.4
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    • pp.299-314
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    • 2014
  • A lifting device is used to deal with transport cask for the transportation of spent fuels from nuclear power plants. This study performed theoretical analysis and numerical simulation to evaluate the structural integrity of the lifting device based on Nuclear Safety and Security Commission(NSSC) Notice No.2013-27 and US 10CFR Part 71 ${\S}71.45$. The results of theoretical analysis showed that the maximum stresses of all components were below the allowable values. This result confirmed that the lifting device was structurally safe during operation. The results of finite element analysis also showed that it was evaluated to satisfy the design criteria bothyielding and ultimate condition. All components have been shown to ensure the structural safety due to sufficient safety margins. In other words, the safety factor was 3 or more for the yielding condition and was 5 or more for the ultimate condition.

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

  • Lee, Seung Yeop;Jeong, Jongtae
    • Journal of the Mineralogical Society of Korea
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    • v.26 no.4
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    • pp.219-228
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    • 2013
  • To understand characteristics of biogeochemical corrosion for the metal canisters that usually contain the radioactive wastes for a long-term period below the ground, some metal materials consisting of cast iron and copper were reacted for 3 months with D. desulfuricans, a sulfate-reducing bacterium, under a reducing condition. During the experiment, concentrations of dissolved metal ions were periodically measured, and then metal specimen and surface secondary products were examined using the electron microscopy to know the chemical and mineralogical changes of the original metal samples. The metal corrosion was not noticeable at the absence of D. desulfuricans, but it was relatively greater at the presence of the bacterium. In our experiment, darkish metal sulfides such as mackinawite and copper sulfide were the final products of biogeochemical metal corrosion, and they were easily scaled off the original specimen and suspended as colloids. For the copper specimen, in particular, there appeared an accelerated corrosion of copper in the presence of dissolved iron and bacteria in solution, probably due to a weakening of copper-copper binding caused by a growth of other phase, iron sulfide, on the copper surface.

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

  • Lee, Jeong Seok;Kim, Wang Bae;Kwak, Dong Ryul
    • Transactions of the Korean Society of Pressure Vessels and Piping
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    • v.16 no.1
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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.

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

  • 강동우;박광수;문길호;엄달선
    • Proceedings of the Korean Radioactive Waste Society Conference
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    • 2003.11a
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    • pp.196-201
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    • 2003
  • Decontamination means every method that can drop the level of the radioactivities from the materials contaminated with them to the allowable one. In this paper, one of the decontamination methods, the electro-decontamination was described with lots of experiments. Two test specimens contaminated with alpha ray and beta ray respectively were used to compare the decontamination factors between two rays and many experiments were performed in every electrolyte with SUS and Carbon steel test specimens. Sulphuric acid, phosphoric acid, nitric acid, citric acid and oxalic acid were used as the electrolyte. Decontamination Factors (DF) could be compared and analyzed with different electrolyte, current intensities and time.

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

  • Kim, Hyochung;Kim, Meera
    • Journal of the East Asian Society of Dietary Life
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    • v.27 no.4
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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
    • Journal of Nuclear Fuel Cycle and Waste Technology(JNFCWT)
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    • v.20 no.3
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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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    • v.55 no.1
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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.

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

  • Kim, Chan Kyu;Moon, Do Yeong;Moon, Il Woo;Cho, Young Tae
    • Journal of the Korean Society of Manufacturing Process Engineers
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    • v.21 no.1
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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.

Measurement Method of Final Residual Radioactivity of Radioactive Metallic Waste for Clearance (규제해제 대상 방사성 금속 폐기물 최종잔류방사능 측정법)

  • Seo, Bumkyoung;Ji, Youngyong;Hong, Sangbum;Lee, Keunwoo;Moon, Jeikwon
    • Journal of Radiation Protection and Research
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    • v.38 no.4
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    • pp.228-233
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    • 2013
  • It has been continuously generated the requirement for the replacement of the main components such as a steam generator due to the deterioration of the nuclear power plant all around the world. Also, a large amount of radioactive metal was generated during the decommissioning in a short period. It is required to make an accurate measurement of the residual radioactivity for recycling the metal waste for releasing from regulatory control. In planning the measurement procedures, the influence of geometry, self-absorption, density and other relevant factors on the representativeness of the measurements should be considered for the decommissioning metal waste. In this study, the method for measurement procedures, the source term evaluation, the ways to secure representative samples, the measurement device for wide area and the self-absorption correction factors for different density were evaluated. The metal samples for measurement were prepared for securing the simple geometry and representative by melting process. The developed correction method for measuring the radioactivity a variety density of metal waste could improve the reliability of the evaluation results for clearance.