• Title/Summary/Keyword: Dismantling procedure

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Scheduling Optimization for Safety Decommissioning of Research Reactor (연구로 안전 해체를 위한 스케쥴링 최적화)

  • Kim, Tae-Sung;Park, Hee-Seoung;Lee, Jong-Hwan;Chang, Sung-Ho;Kim, Sang-Ho
    • Journal of the Korea Safety Management & Science
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    • v.8 no.3
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    • pp.67-75
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    • 2006
  • Scheduling of dismantling old research reactor need to consider time, cost and safety for the worker. The biggest issue when dismantling facility for research reactor is safety for the worker and cost. Large portion of a budget is spending for the labor cost. To save labor cost for the worker, reducing a lead time is inevitable. Several algorithms applied to reduce read time, and safety considered as the most important factor for this project. This research presents three different dismantling scheduling scenarios. Best scenario shows the specific scheduling for worker and machine, so that it could save time and cost.

Requirement Management through Connection between Regulatory Requirements and Technical Criteria for Dismantling of Nuclear Installations (원자력시설 해체 규제요건과 기술기준 연계를 통한 요구관리)

  • Park, Hee Seoung;Park, Jong Sun;Hong, Yun Jeong;Kim, Jeong Guk;Hong, Dae Seok
    • Journal of the Korean Society of Systems Engineering
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    • v.14 no.1
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    • pp.63-71
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    • 2018
  • This paper discusses decommissioning procedure requirements management using requirement engineering to systematically manage the technical requirements and criteria that are required in decontamination and decommissioning activities, and the regulatory requirements that should be complied with in a decommissioning strategy for research reactors and nuclear power plants. A schema was designed to establish the traceability and change management related to the linkage between the regulatory requirements and technical criteria after classifying the procedures into four groups during the full life-cycle of the decommissioning. The results confirmed that the designed schema was successfully traced in accordance with the regulatory requirements and technical criteria required by various fields in terms of decontamination and decommissioning activities. In addition, the changes before and after the revision of the Nuclear Safety Act were also determined. The dismantling procedure requirement management system secured through this study is expected to be a useful tool in the integrated management of radioactive waste, as well as in the dismantling of research reactor and nuclear facilities.

Development on Test Procedure of Pitch and Yaw Bearings for Wind Turbine (풍력발전기용 피치/요 베어링의 시험절차 개발)

  • Nam, Ju Seok;Han, Jeong Woo
    • Journal of the Korean Society of Manufacturing Technology Engineers
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    • v.24 no.3
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    • pp.355-362
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    • 2015
  • Test procedure for the design verification of wind turbine pitch and yaw bearings has been developed. Test items were selected to evaluate operational reliability of pitch and yaw bearings by considering loading and operational conditions, and by analyzing the design criteria of pitch and yaw bearings. The developed test items consisted of preliminary test, fatigue load test, extreme load test, low temperature environmental test and dismantling inspection after all the test were completed. Because it reflects the actual operational conditions of the pitch and yaw bearings, the developed test procedure has high reliability and can verify the basic design considerations in the international standard and guidelines.

Reassessment on the Four Major Rivers Restoration Project and the Weirs Management (4대강 살리기사업의 재평가와 보의 운용방안)

  • Lee, Jong Ho
    • Journal of Environmental Impact Assessment
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    • v.30 no.4
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    • pp.225-236
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    • 2021
  • The master plan for the Four Rivers Restoration Project (June 2009) was devised, the procedure of pre-environmental review (June 2009) and environmental impact assessment (Nov. 2009), and post-environmental impact survey were implemented, and 4 times audits also inspected. and finally the Ministry of Environment's Four Rivers Investigation and Evaluation Planning Committee proposed the dismantling or partial dismantling of the five weirs of the Geum River and Yeongsan River. But controversies and conflicts are still ongoing. Therefore, this study intend to reestablish the management plan for the four major rivers by reviewing and analyzing the process so far. The results are as follows. First, a cost-benefit analysis should be performed by comparing the water quality impact of weir operation and weir opening. Therefore, it is inevitably difficult to conduct cost-benefit analysis. Second, according to the results of cost-benefit analysis on the dismantling of the Geum River and the Yeongsan River, the dismantling of the weir and the regular sluice gate opening was decided. However, there is a problem in the validity of the decision to dismantle the weir because the cost-benefit analysis for maintaining the weir is not carried out. Third, looking at the change in water quality of 16 weirs before and after the Four Major Rivers Restoration Project, COD and Chl-a were generally deteriorated, and BOD, SS, T-N, and T-P improved. However, in the cost-benefit analysis related to water quality at the time of weir dismantling, only COD items were targeted. Therefore, the cost of BOD, SS, T-N, and T-P items improved after the project were not reflected in the cost-benefit analysis of dismantling weirs, so the water quality benefits were exaggerated. Fourth, in the case of Gongju weir and Juksan weir, most of them are movable weirs, so opening the weir alone can have the same effect as dismantling when the water quality deteriorates. Since the same effect can be expected, there is little need to dismantle the weirs. Fifth, in order to respond to frequent droughts and floods, it is desirable to secure the agricultural water supply capacity to the drought areas upstream of the four majorrivers by constructing a waterway connected to the weir. At present it is necessary to keep weirs rather than dismantling them.

The Component of the 3D CAD Modelling through the Review of Dismantling Procedure on a Core Part in the KRR-2 (연구로 2호기 노심 부분 해체 절차 검토를 통한 3D CAD 모델링 구성요소의 도출)

  • 김희령;박승국;정운수;정기정
    • Proceedings of the Korea Society for Energy Engineering kosee Conference
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    • 2002.05a
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    • pp.129-134
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    • 2002
  • 상업용 원자력 발전소와 연구용 원자로, 재처리시설 또는 원자력 관련 연구시설 등은 일반적으로 한계수명의 도달, 정치 경제적 사유 또는 안전성 둥의 이유로 폐지조치 하게 된다. 현재 세계적으로 80여기 이상의 발전소와 수백 개의 연구시설, 연구로 및 재처리 시설 등이 폐로 중에 있거나 대기중이다.(중략)

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High-power fiber laser cutting parameter optimization for nuclear Decommissioning

  • Lopez, Ana Beatriz;Assuncao, Eurico;Quintino, Luisa;Blackburn, Jonathan;Khan, Ali
    • Nuclear Engineering and Technology
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    • v.49 no.4
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    • pp.865-872
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    • 2017
  • For more than 10 years, the laser process has been studied for dismantling work; however, relatively few research works have addressed the effect of high-power fiber laser cutting for thick sections. Since in the nuclear sector, a significant quantity of thick material is required to be cut, this study aims to improve the reliability of laser cutting for such work and indicates guidelines to optimize the cutting procedure, in particular, nozzle combinations (standoff distance and focus position), to minimize waste material. The results obtained show the performance levels that can be reached with 10 kW fiber lasers, using which it is possible to obtain narrower kerfs than those found in published results obtained with other lasers. Nonetheless, fiber lasers appear to show the same effects as those of $CO_2$ and ND:YAG lasers. Thus, the main factor that affects the kerf width is the focal position, which means that minimum laser spot diameters are advised for smaller kerf widths.

Development of a Methodology for Estimating Radioactivity Concentration of NORM Scale in Scrap Pipes Based on MCNP Simulation

  • Wanook Ji;Yoomi Choi;Zu-Hee Woo;Young-Yong Ji
    • Journal of Nuclear Fuel Cycle and Waste Technology(JNFCWT)
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    • v.21 no.4
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    • pp.481-487
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    • 2023
  • Concerning the apprehensions about naturally occurring radioactive materials (NORM) residues, the International Atomic Energy Agency (IAEA) and its member nations have acknowledged the imperative to ensure the radiation safety of NORM industries. Residues with elevated radioactivity concentrations are predominantly produced during NORM processing, in the form of scale and sludge, referred to as technically enhanced NORM (TENORM). Substantial quantities of TENORM residues have been released externally due to the dismantling of NORM processing factories. These residues become concentrated and fixed in scale inside scrap pipes. To assess the radioactivity of scales in pipes of various shapes, a Monte Carlo simulation was employed to determine dose rates corresponding to the action level in TENORM regulations for different pipe diameters and thicknesses. Onsite gamma spectrometry was conducted on a scrap iron pipe from the titanium dioxide manufacturing factory. The measured dose rate on the pipe enabled the estimation of NORM concentration in the pipe scale onsite. The derived action level in dose rate can be applied in the NORM regulation procedure for on-site judgments.

Feasibility Analysis for Introduction of Scaffolding with Advanced Guardrail System to Prevent Falls (비계작업의 추락재해예방을 위한 선행 안전난간 공법의 도입 타당성 분석)

  • Park, J.D.;Moon, S.O.;Lee, H.S.;Jeong, S.C.;Kwon, Y.J.;Jung, K.
    • Journal of the Korean Society of Safety
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    • v.35 no.4
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    • pp.23-31
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    • 2020
  • In the construction sector, there were 99 fatalities from falls associated with steel tube and system scaffolds for three years from 2016 to 2018 and out of which 27.3 percent (27 workers) were found to have occurred during installing and dismantling procedure. To erect scaffolding which is installed for the work at height, the work platforms are generally installed first and the safety guardrails are installed and vice versa to dismantle. As a result, workers are exposed to the risk of falling because they erect and dismantle scaffolding without guardrails. To minimize the risk of falling, it is necessary to study a new construction method that can erect or dismantle scaffolding while guardrails are installed (called advanced guardrail system). This study analyzed advanced guardrail system in terms of safety regulation, workability and economic efficiency by investigating the domestic situation on the use of scaffolding, reviewing domestic and foreign standards for guardrails and conducting economic feasibility study. The results of this study is expected to greatly contribute to preventing falls in scaffolding installation and dismantlement procedure. As a follow-up study, empirical research is required including physical test of scaffolding with advanced guardrail system and effectiveness analysis after trial applications.