• Title/Summary/Keyword: Radioactive Waste Management

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Verification of the adequacy of domestic low-level radioactive waste grouping analysis using statistical methods

  • Lee, Dong-Ju;Woo, Hyunjong;Hong, Dae-Seok;Kim, Gi Yong;Oh, Sang-Hee;Seong, Wonjun;Im, Junhyuck;Yang, Jae Hwan
    • Nuclear Engineering and Technology
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    • v.54 no.7
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    • pp.2418-2426
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    • 2022
  • The grouping analysis is a method guided by the Korea Radioactive Waste Agency for efficient analysis of radioactive waste for disposal. In this study, experiments to verify the adequacy of grouping analysis were conducted with radioactive soil, concrete, and dry active waste in similar environments. First, analysis results of the major radionuclide concentrations in individual waste samples were reviewed to evaluate whether wastes from similar environments correspond to a single waste stream. As a result, the soil and concrete waste were identified as a single waste stream because the distribution range of radionuclide concentrations was "within a factor of 10", the range that meet the criterion of the U.S. Nuclear Regulatory Commission for a single waste stream. On the other hand, the dry active waste was judged to correspond to distinct waste streams. Second, after analyzing the composite samples prepared by grouping the individual samples, the population means of the values of "composite sample analysis results/individual sample analysis results" were estimated at a 95% confidence level. The results showed that all evaluation values for soil and concrete waste were within the set reference values (0.1-10) when five-package and ten-package grouping analyses were conducted, verifying the adequacy of the grouping analysis.

Calcium Sulfo Aluminate (CSA) Cement from Coal Ash Utilized as Barriers for Radioactive Waste Disposal

  • Ramakrishna, Chilakala;Thriveni, Thenepalli;Whan, Ahn Ji
    • Journal of Energy Engineering
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    • v.27 no.1
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    • pp.33-39
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    • 2018
  • In this paper, we reviewed briefly about the barrier materials for the radioactive waste disposal. The primary concept of the radioactive waste disposal is safety. The goal of the radioactive waste management is to assure that the environment is not adversely affected and also public. There are a wide variety of materials are available for the radioactive waste disposal or storage. Among those coal fly ash is one of the significant materials are used as a barrier material. Here we reported, the Calcium sulfo aluminate (CSA) from coal fly ash is effectively suitable for the radioactive waste disposal. This is one of the ways of utilization of waste and manufactured the valuable materials for future indeeds.

Analysis of the Awareness of Medical Radioactive Waste Management Plans (with Focus on Busan and Gyeongsangnam-do) (의료방사성폐기물 관리방안에 대한 인식 분석 - 부산, 경남을 중심으로 -)

  • Kang, Se-Sik;Choi, Seok-Yoon;Kim, Jung-Hoon
    • Journal of radiological science and technology
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    • v.37 no.1
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    • pp.29-36
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    • 2014
  • This study was conducted to propose medical radioactive waste management methods by background factors of radioactive workers, their awareness of safety management and reduce the difficulty of self-disposal. A population of 102 radiotechnologist who work at hospital in Busan was the subject of this study and a survey was conducted to them. the analysis for the collected data used SPSS/PC+Win13 version and one-way, ANOVA was carried out of verify differences between the groups. The result showed that most of workers had correct awareness of radioactive waste management. Also, about the difficulty of self-disposal, legal procedures were mentioned most often, and as efficient improvement of management methods is concerned, changing the awareness of safety management and disposal was proposed. According to this study, the right way of managing medical radioactive waste is to change the awareness of radioactive workers by reinforcing regular training.

Radioactive Waste Integrated Management System (방사성폐기물 통합 관리 시스템)

  • 송덕용;최성수;한병섭
    • Proceedings of the Korean Radioactive Waste Society Conference
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    • 2003.11a
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    • pp.572-578
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    • 2003
  • In this paper, we present an integrated management system for radioactive waste, which can keep watch on the whole transporting process of each drum from nuclear power plant temporary storage house to radioactive waste storage house remotely. Our approach use RFID(Radio Frequency Identification) system, which can recognize the data information without touch, GSP system, which can calculate the current position precisely using the accurate time and distance measured from satellites, and the spread spectrum technology CDMA, which is widely used in the area of mobile communication.

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Chemical Treatment of Low-level Radioactive Liquid Waste (I)

  • Lee, Sang-Hoon;Choe, Jong-In;Kim, Yong-Eak
    • Nuclear Engineering and Technology
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    • v.8 no.2
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    • pp.69-76
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    • 1976
  • This experiment has been carried out for the removal of long-lived radioactive-nuclides (Sr-90, Ru-106, Cs-137 and Ce-144) contained in the low-level radioactive effluents from the spent fuel reprocessing plant and nuclear power plant, in order to determine the decontaminability of various chemical coagulants and domestic clay mineral (montmorillonite). Phosphate process showed prominent efficiency for the removal of Ce-144, and lime-soda process did good removal efficiency for Sr-90. About Cs-137 copper-ferrocyanide process is much desirable. In phosphate or lime-soda process, most favorable removal efficiency was obtained at more than pH 11. The montmorillonite treated with sodium chloride showed a considerable improvement in the removal of the radioactive-nuclides. By a combined chemicals-montmorillionite process, the radioactive-nuclides could be more effectively removed than by the only chemicals process.

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Conceptual Design and Development of an Automatic Classification System According to Radioactive Contamination Level Measurement and Contamination of Radioactive Metal Waste (방사성 금속폐기물의 방사능 오염도 측정 및 오염 여부에 따른 자동 분류 시스템 개념설계 및 개발)

  • Sun Beom Kwon;Bo Gil Kim;Jeong Min Yeom;Gyeong Mo Lee;Hong Yeon Lee;Sang Jun Han
    • Journal of Radiation Industry
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    • v.17 no.1
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    • pp.11-17
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    • 2023
  • Waste generated during the dismantling of nuclear power plants is not only diverse in types such as metal, concrete, soil, but also in a large amount, requiring systematic and efficient management. It is very important to quickly and accurately measure radioactive contamination of wastes generated simultaneously at the decommissioning site, classify them by level, and make decisions so that they can be disposed of in accordance with related laws and regulations. In this paper, for the technical and economic aspects of recycling of radioactive metal waste generated during the dismantling of nuclear power plants, we propose a management system that can measure the radioactive contamination by shape of metal waste at the decommissioning site and automatically classify it according to the presence or absence of contamination. Accordingly, a system for collecting information on metal samples such as weight measurement and shape acquisition of metal waste, measurement of radioactive contamination and identification of nuclides, and an automatic classification system according to radioactivity measurement results were described.