• Title/Summary/Keyword: Waste Disposal Cost

Search Result 140, Processing Time 0.022 seconds

A Study of the Decommissioning Cost Estimation for Nuclear Facilities (원자력 시설 해체비용 산정에 관한 고찰)

  • 이동규;정관성;이근우;오원진
    • Proceedings of the Korean Radioactive Waste Society Conference
    • /
    • 2004.06a
    • /
    • pp.85-96
    • /
    • 2004
  • This paper is to study on the decommissioning cost estimation for nuclear facilities of advanced nuclear organizations and countries for deriving the cost factors to be taken considerations into accomplishing decommissioning projects. Of cost categories producing the factors of decommissioning costs, dismantling and waste processing & disposals activities are examined to increase the its costs. Of labor, materials and other costs categories, labor costs are summarized to have overall majorities in the decommissioning cost factors. The main parameters of all factors affecting the decommissioning costs are analyzed as work difficulty, regional labor costs, peripheral cost, disposal cost and final burial costs.

  • PDF

Suggestion of Efficient High Dose Spent Filter Handling and Compaction Equipment

  • Lee, Kyungho;Chung, Sewon;Park, Seonghee;Kim, HuiGyeong
    • Journal of Nuclear Fuel Cycle and Waste Technology(JNFCWT)
    • /
    • v.20 no.2
    • /
    • pp.243-253
    • /
    • 2022
  • Spent filters with a high radiation dose rate of 2 mSv·hr-1 or more are not easily managed. So far, the Korean policy for spent filter disposal is to store them temporarily at nuclear power plants until the waste filters can be easily managed. Nuclear power plant decommissioning in Korea is starting with Kori unit 1. Volume reduction of waste generated during decommissioning can reduce the cost and optimize the space usage at disposal site. Therefore, efficient volume reduction is a very important factor during the decommissioning process. A conceptual method, based on the experiences of developing 200 and 800 ton compactors at Orion EnC, has been developed considering worker exposure with the followings a crusher (upgrade of compaction efficiency), an automatic dose measuring system with a NaI(Tl) detector, a shield box, an inner drum to prepare for easy handling of drums and packaging, a 30 ton compactor, and an automatic robot system. This system achieves a volume reduction ratio of up to 85.7%; hence, the system can reduce the disposal cost and waste volume. It can be applied to other types of wastes that are not easily managed due to high dose rates and remote control operation necessity.

Concepts of heat dissipation of a disposal canister and its computational analysis

  • Minseop Kim;Minsoo Lee;Jinseop Kim;Seok Yoon
    • Nuclear Engineering and Technology
    • /
    • v.55 no.11
    • /
    • pp.4173-4180
    • /
    • 2023
  • The stability of engineered barriers in high-level radioactive waste disposal systems can be influenced by the decay heat generated by the waste. This study focuses on the thermal analysis of various canister designs to effectively lower the maximum temperature of the engineered barrier. A numerical model was developed and employed to investigate the heat dissipation potential of copper rings placed across the buffer. Various canister designs incorporating copper rings were presented, and numerical analysis was performed to identify the design with the most significant temperature reduction effect. The results confirmed that the temperature of the buffer material was effectively lowered with an increase in the number of copper rings penetrating the buffer. Parametric studies were also conducted to analyze the impact of technical gaps, copper thickness, and collar height on the temperature reduction. The numerical model revealed that the presence of gaps between the components of the engineered barrier significantly increased the buffer temperature. Furthermore, the reduction in buffer temperature varied depending on the location of the gap and collar. The methods proposed in this study for reducing the buffer temperature hold promise for contributing to cost reduction in radioactive waste disposal.

Survey on the Current Disposal Practices of Food Waste left by Patients & Staff in 20 Hospital Foodservices (병원급식소의 환자 및 직원 잔식의 처리 현황 조사)

  • Kim, Hye-Jin;Hong, Wan-Su
    • Journal of the Korean Dietetic Association
    • /
    • v.2 no.2
    • /
    • pp.158-167
    • /
    • 1996
  • Food waste left by patients in hospitals is an important indicator of the nutritional adequacy of the patients' diet and of their satisfaction with food. Food wasted by patients or staff in hospitals is one of the most serious problem in hospital foodservice systems. The purpose of this study was to evaluate the disposal practices of food waste in hospital foodservices for providing basic information for an efficient solid waste management. This approach was achieved using a variety of qualitative and quantitative information including general food waste practices and measurement of food waste left by patients and staff in 20 hospital foodservices. The average food wasted by patients and staff per day was 402.20kg and 206.98kg respectively, being total food waste of 578.08kg per day. The mean plate waste of a staff was 115.95g, which was much lower than that of a patient (221.03g). As means of food waste treatment, most hospitals(60%) are using animal feed, followed by means of collection by contracters(15%) and disposal of waste collection after condensing. An average monthly cost for disposing food waste was 915,000 won and average 138.58 minutes were spent to dispose food waste in hospital foodservices.

  • PDF

The Study on Solid Waste Management in School Foodservices in the Kyungbuk Area (경북지역 학교급식에서의 쓰레기 관리에 관한 연구)

  • 정상렬;이혜상
    • Korean Journal of Community Nutrition
    • /
    • v.6 no.5
    • /
    • pp.837-847
    • /
    • 2001
  • The main purposes of this study were to survey and assess the current situation surrounding solid waste generation in school foodservices, to identify and evaluate the measures(reduction and recycling programs) taken by the foodservices for waste disposal, and to suggest appropriate reform measures to improve the current status, especially in terms of environmental preservation. Questionnaires on solid waste management practices were mailed to 206 school foodservice dietitians in the Kyungbuk region : a 64.0%(N = 130) response rate was obtained. While there are food waste and packaging waste generated from the foodservice operations, about a third(34.1%) of the foodservice operations were responsible for the disposal of both the food wastes and packaging wastes. About 90% of school foodservice managers were responsible for managing solid wastes. The primary recycling methods of leftovers generated from the school food service operations were livestock feed(76.0%). About 60.0% of school foodservice managers conducted the food waste reduction program. The performance by the foodservice managers in reducing the food waste was not satisfactory in several fields, such as developing environmentally friendly menus or abiding by the standard recipe, etc. In addition, the government assistance system was not properly working in the food service management. In conclusion, we should focus on increasing the performance in reducing the food waste by the foodservice managers, strengthening and facilitating the government assistance system for the food waste management and to develop education methods and education materials for food waste management.

  • PDF

Analysis of dismantling process and disposal cost of waste RVCH

  • Younkyu Kim;Sunkyu Park ;TaeWon Seo
    • Nuclear Engineering and Technology
    • /
    • v.55 no.1
    • /
    • pp.45-51
    • /
    • 2023
  • During the operation of a nuclear power plant (NPP), the waste reactor vessel closure head (RVCH) that is replaced owing to design or manufacturing defects is buried in a designated area or temporarily stored in a radiation shielding facility within the NPP. In such cases, storing it for extended periods proves a challenge owing to space constraints in the power plant and a safety risk associated with radiation exposure; therefore, dismantling it quickly and safely is crucial. However, not much research has been done on the dismantling of the RVCH in an operational power plant. This study proposes a dismantling process based on the radioactive contamination level measured for the Kori #1 RVCH, which is currently being discarded and stored, and examines the decontamination and cutting according to this process. In addition, the amount of secondary waste and dismantling cost are evaluated, and the dismantling effect of the reactor closure head is analyzed.

The ROK Nuclear Power Programme -Some Aspects of Radioactive Waste Management in the Nuclear Fuel Cycle-

  • West, P.J.
    • Nuclear Engineering and Technology
    • /
    • v.12 no.3
    • /
    • pp.194-213
    • /
    • 1980
  • The paper describes and quantifies the wastes arising in the nuclear fuel cycle for Light Water Reactors, Heavy Water Reactors and Fast Breeder Reactors. The management and disposal technologies are indicated, together with their environmental impacts. Both once-through and uranium-plutonium recycle systems are evaluated, and comparisons are made on the basis of tingle reference technologies for waste management, and for one gigawatt/year of electricity generation. Environmental impacts are assessed, particularly that of health and safety, and a reference costing system is applied purely as a basis for comparing the fuel cycles. From this study it call be concluded generally that the relative differences of the impacts of waste management and disposal between the selected fuel cycles are not decisive factors in choosing a fuel cycle. Employing the technologies assumed, the radioactive wastes from any of the fuel cycles studied can be managed and disposed of with a high degree of safety and without undue risk to man or the environment. The cost of waste management and disposal is only a few percent of the value of the electricity generated and does not vary greatly between fuel cycles.

  • PDF

The Dismantling and Disposal Strategy of a Biological Shield for Minimization of Radioactive Concrete Waste During Decommissioning of a Nuclear Power Plant (원전 해체 방사성 콘크리트 폐기물 최소화를 위한 생물학적 차폐체 제거 및 처분 전략)

  • Cheon, Cheol-Seung;Kim, Chang-Lak
    • Journal of Nuclear Fuel Cycle and Waste Technology(JNFCWT)
    • /
    • v.15 no.4
    • /
    • pp.355-367
    • /
    • 2017
  • The decommissioning of Kori unit 1, which was permanently shut down in June of 2017, will be the first instance of the dismantling of a commercial nuclear power plant in Korea. The disposal of waste during the dismantling process accounts for a large part of the total decommissioning cost. Therefore, structures consisting of activated and contaminated concrete must be economically and safely dismantled by establishing a proper dismantling strategy. This study focuses on optimized dismantling and disposal scenarios pertaining to a biological shield. Several dismantling cases, regulations and technologies related to waste treatment as these practices pertain to nuclear power plants are analyzed. To minimize the amount of waste from the biological shield dismantling process, an optimized dismantling scenario is presented and disposal alternatives for dismantled concrete waste are proposed.

Consideration on supplementary matters when preparing radioactive waste self-disposal (방사성폐기물 자체처분 작성시 보완사항에 관한 고찰)

  • Lee, Kyung-Jae;Park, Sung-woo;Park, Young-Jae;Park, In-Sik
    • The Korean Journal of Nuclear Medicine Technology
    • /
    • v.26 no.1
    • /
    • pp.15-26
    • /
    • 2022
  • Purpose Recently, in the process of examining the self-disposal of radioactive waste by the Korea Institute of Nuclear Safety, it is difficult to reach the final approval process for self-disposal. In connection with this, we intend to increase the processing efficiency of self-disposal and strengthen safety by analyzing cases of recent supplementary matters. Materials and Methods From 2018 to 2021, we compare and review a supplementary requests that preparing the procedures and plans for the self-disposal of radioactive waste by 20 institutions. In this regard, based on the provisions of the Atomic Energy Safety Act, we derive a detailed proposals for the self-disposal of radioactive waste by arranging the review processing period calculation and supplementary requests that occurred during the review process. Results The representative supplementary requests of the Korea Institute of Nuclear Safety are the calculation of the storage period by type and nuclide of radioactive waste, the contents of the packaging container, the RASIS reporting method, the planned storage method for self-disposal, confirmation of the final disposal company, and the storage period of the waste filter Calculation, radioactive labeling, etc. And it is emphasized as important. Conclusion The expected effects of the guidelines reflecting the latest supplements include reduction of the time required for document preparation and increase of work processing efficiency, improvement of storage efficiency in the radioactive waste storage room, and economic cost reduction. If the radioactive waste self-disposal guideline presented in this study is applied to the field, it is thought that it will be helpful in improving the work efficiency of those who are experiencing difficulties.

Illustration of Nagra's AMAC approach to Kori-1 NPP decommissioning based on experience from its detailed application to Swiss NPPs

  • Volmert, Ben;Bykov, Valentyn;Petrovic, Dorde;Kickhofel, John;Amosova, Natalia;Kim, Jong Hyun;Cho, Cheon Whee
    • Nuclear Engineering and Technology
    • /
    • v.53 no.5
    • /
    • pp.1491-1510
    • /
    • 2021
  • This work presents an illustration of Nagra's AMAC (Advanced Methodology for Activation Characterization) approach to the South Korean pressurized water reactor Kori-1 decommissioning. The results achieved are supported by the existing experience from the detailed AMAC applications to Swiss NPPs and are used not only for a demonstration of the applicability of AMAC to South Korean NPPs, but also for a first approximation of the activated waste volumes to be expected from Kori-1. A packaging concept based on the above activation characterization is also presented, using the AMAC algorithmic optimization software ALGOPACK leading to the minimum number of waste containers needed given the selected packaging constraints. Nagra's AMAC enables effective planning before and during NPP decommissioning, including recommendations for cutting profiles for diverse reactor components and building structures. Finally, it is expected to lead to significant cost savings by reducing the number of expensive waste containers, by optimizing a potential melting strategy for metallic waste as well as by significantly limiting the number of radiological measurements. All information about Kori-1 used for the purpose of this study was collected from publicly available sources.