• Title/Summary/Keyword: Safe-site

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Usefulness of an Additional Mattress Suture for the Extracranial Drainage Catheter

  • Eom, Dong Woong;Kim, Jung Soo;Jeon, Kyoung Dong;Kim, Hoon;Choi, Byeong Sam
    • Journal of Korean Neurosurgical Society
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    • v.54 no.5
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    • pp.444-447
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    • 2013
  • In most intracranial surgery cases, a drain catheter is inserted to prevent the collection of the wound hematoma or seroma. A drain catheter is also inserted to drain the hematoma or the cerebrospinal fluid. The drain catheter itself does not cause complications; but many complications occur during its removal, such as hematoma, seroma, air collection and pseudomeningocele formation. To prevent these complications, neurosurgeons perform a suture on the catheter to remove the site. In this study, an additional horizontal mattress suture and an anchoring suture to the drainage catheter are proposed. This method maintains negative pressure in the catheter insertion site during the catheter removal, compresses the catheter tunnel site and attaches the external wounds strongly. The technique is easy and safe to perform, and does not require an additional suture to remove the catheter.

The Swiss Radioactive Waste Management Program - Brief History, Status, and Outlook

  • Vomvoris, S.;Claudel, A.;Blechschmidt, I.;Muller, H.R.
    • Journal of Nuclear Fuel Cycle and Waste Technology
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    • v.1 no.1
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    • pp.9-27
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    • 2013
  • Nagra was established in 1972 by the Swiss nuclear power plant operators and the Federal Government to implement permanent and safe disposal of all types of radioactive waste generated in Switzerland. The Swiss Nuclear Energy Act specifies that these shall be disposed of in deep geological repositories. A number of different geological formations and sites have been investigated to date and an extended database of geological characteristics as well as data and state-of-the-art methodologies required for the evaluation of the long-term safety of repository systems have been developed. The research, development, and demonstration activities are further supported by the two underground research facilities operating in Switzerland, the Grimsel Test Site and the Mont Terri Project, along with very active collaboration of Nagra with national and international partners. A new site selection process was approved by the Federal Government in 2008 and is ongoing. This process is driven by the long-term safety and feasibility of the geological repositories and is based on a step-wise decision-making approach with a strong participatory component from the affected communities and regions. In this paper a brief history and the current status of the Swiss radioactive waste management program are presented and special characteristics that may be useful beyond the Swiss program are highlighted and discussed.

Offsite Risk Assessment on Toxic Release (독성물질 저장설비의 사고시 사업장외에 미치는 영향평가)

  • Park, Kyoshik
    • Journal of the Korean Institute of Gas
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    • v.21 no.3
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    • pp.9-16
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    • 2017
  • Toxic release is one of the most interested area in evaluating consequence to the vicinity of industry facilities handling hazardous materials. Chloric acid production facility is selected and toxic release is evaluated to assess the risk impacted to its off-site. Accident scenarios were listed using process safety information. The scenarios having effect to the off-site were selected and assessed further according to guideline provided by Korea government. Worst case and alternative scenarios including other interested scenarios were evaluated using ALOHA. Each evaluated scenario was assessed further considering countermeasures. The results showed that the facility handling chloric acid is safe enough and needed no further protections at the moment.

ROLE OF SOILS IN THE DISPOSAL OF NUCLEAR WASTE

  • Lee, S.Y.
    • Korean Journal of Soil Science and Fertilizer
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    • v.19 no.3
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    • pp.251-268
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    • 1986
  • Selecting a site for the safe disposal of radioactive waste requires the evaluation of a wide range of geologic, mineralogic, hydrologic, and physicochemical properties. Although highly diverse, these properties are in fact interrelated. Site requirements are also diverse because they are influenced by the nature of the radionuclides in the waste, for example, their half-lives, specific energy, and chemistry. A fundamental consideration in site selection is the mineralogy of the host rock, and one of the most ubiquitous mineral groups is clay minerals. Clays and clay minerals as in situ lithologic components and engineered barriers may playa significant role in retarding the migration of radionuclides. Their high sorptivity, longevity (stability), low permeability, and other physical factors should make them a very effective retainer of most radionuclides in nuclear wastes. There are, however, some unanswered questions. For example, how will their longevity and physicochemical properties be influenced by such factors as radionuclide concentration, radiation intensity, elevated temperatures, changes in redox condition, pH, and formation fluids for extended periods of time? Understanding of mechanisms affecting clay mineral-radionuclide interactions under prevailing geochemical conditions is important; however, the utilization of experimental geochemical information related to physicochemical properties of clays and clay-bearing materials with geohydrologic models presents a uniquely challenging problem in that many assessments have to be based on model predictions rather than on experiments. These are high-priority research investigations that need to be addressed before complete reliance for disposal area performance is made on clays and clay minerals.

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Countermeasures for Management of Off-site Radioactive Wastes in the Event of a Major Accident at Nuclear Power Plants

  • Lee, Ji-Min;Hong, Dae Seok;Shin, Hyeong Ki;Kim, Hyun Ki
    • Journal of Nuclear Fuel Cycle and Waste Technology(JNFCWT)
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    • v.20 no.3
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    • pp.339-347
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    • 2022
  • Major accidents at nuclear power plants generate huge amounts of radioactive waste in a short period of time over a wide area outside the plant boundary. Therefore, extraordinary efforts are required for safe management of the waste. A well-established remediation plan including radioactive waste management that is prepared in advance will minimize the impact on the public and environment. In Korea, however, only limited plans exist to systematically manage this type of off-site radioactive waste generating event. In this study, we developed basic strategies for off-site radioactive waste management based on recommendations from the IAEA (International Atomic Energy Agency) and NCRP (National Council on Radiation Protection and Measurements), experiences from the Fukushima Daiichi accident in Japan, and a review of the national radioactive waste management system in Korea. These strategies included the assignment of roles and responsibilities, development of management methodologies, securement of storage capacities, preparation for the use of existing infrastructure, assurance of information transparency, and establishment of cooperative measures with international organizations.

A Radionuclides Suite Selection for Site Characterization and Final Status Survey in the U.S. NPPs (미국의 원전 해체관련 부지특성 및 최종상태 조사를 위한 방사성 오염 핵종 결정 방법에 대한 분석)

  • Zhao, Pengfei;Jeon, Yeo Ryeong;Kim, Yongmin;Lee, Jong Seh;Ahn, Seokyoung
    • Journal of Nuclear Fuel Cycle and Waste Technology(JNFCWT)
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    • v.14 no.3
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    • pp.267-277
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    • 2016
  • For the decommissioning of a nuclear power plant, a site characterization and final status survey require a site-specific suite of radionuclides that could potentially still be present in the site during or after the decontamination processes. The United States Nuclear Regulatory Commission (U.S. NRC) requires a Decommissioning Technical Base Document (DTBD) along with a Site Characterization and Historical Site Assessment (HSA) from the utility for decommissioning to proceed. Both the DTBD and HSA are preliminary components of the Radiological Site Survey investigation process and should be included in the final License Termination Plan (LTP) for site release and reuse consideration from the U.S. NRC and the utility company. This study reviews the United States Nuclear Power Plants (U.S. NPPs) decommissioning cases and is especially focused on the methodologies used for determining a site-specific suite of radionuclides before and during the site characterization and final status surveys. In 2017, Kori-1 will be ready for decommissioning and related preparations are ongoing, this review will help Korea to prepare regulatory guidelines and give technical background for the safe and successful decommissioning of NPPs.

Displacement and Stress Monitoring for Excavation Deep Foundation (인접지역의 깊은 터파기 굴착에서 변위 및 응력의 계측)

  • 원연호
    • Explosives and Blasting
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    • v.17 no.1
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    • pp.27-55
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    • 1999
  • The excavation works for deep foundation in urban areas have recently increased complaints of blasting vibration and settlement of ground level. Foundation must be excavated approximately up to 24-28m depths from the surface. The roads and subway line pass through the excavation area. The Dae-chung station is also located at the nearest distance 5-35m from the working site. To protect subway station and adjacient some structures from blasting and settlement, the level of ground vibration, displacements and stress were monitored and analyzed. The results can be summarized as follows ; 1. An empirical particle velocity equation were obtained by test blasts at Nassan Missi 860 Office tel construction site. $V{\;}={\;}K(D/\sqrt{W})^{-n}$, where the values for n and k are estimated tobe 0.371 and 1.551. From this ground vibration equation, the max. charge weight per delay time against distance from blasting point is calculated. Detailed blasting method is also presented. 2. To measure the horizontal displacement in directions perpendicular to the borehole axis, 6 inclinometers installed around working sites. The displacement at the begining was comparatively high because the installation of struts was delayed, but after its installation the values showed a stable trend. Among them, the displacement by 3 inclinometers installed on a temporary parking area showed comparatively high values, for example, the displacement measured at hole No. IC-l recoded the max. 47.04mm for 6 months and at hole No. IC-2 recorded the max. 57.33mm for 7 months. So, all of these data was estimated below a safe standard value 103mm. 3. Seven strain gauge meter was installed of measure the magnitude and change of stress acted on structs. The measured value of maximum stress was $-465{\;}kgf/\textrm{cm}^2,{\;}-338.4{\;}kgf/\textrm{cm}^2,{\;}302.3{\;}kgf/\textrm{cm}^2$ respectively. In compareto the allowable stress level of steel, they are estimated to be safe.

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Suggestions for Increasing Utilization of KORA for Supporting the Off-site Risk Assessment System (화학사고 장외영향평가 지원 프로그램(KORA)의 활용도 증대를 위한 제언)

  • Kim, Jungkon;Ryu, Jisung;Ryu, Taekwon;Kwak, Sollim;Lim, Hyeongjun;Choi, Woosoo;Jung, Jinhee;Lee, Jieun;Lim, Dongyeon;Yoon, Junheon
    • Journal of Environmental Health Sciences
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    • v.44 no.2
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    • pp.124-132
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    • 2018
  • Objectives: All enterprises intending to install and operate hazardous chemical handling facilities should prepare an off-site risk assessment (ORA) report that evaluates the impact of potential chemical accidents on the surrounding environment and population. This study was conducted to introduce the process of development and the functioning of the Korea Off-site Risk Assessment support tool (KORA) developed by the National Institute of Chemical Safety and to suggest manners to increase its utilization. Additionally, this article provided an overview of KORA. Methods: In order to identify problems with and refinements for KORA, the required items for each phase of KORA were derived by analyzing the Chemical Control Act and related administrative regulations. Results: The functions of KORA made receptor-considered assessment of chemical accidents possible, but several limitations were found in particular phases, such as the analysis of impact range, consideration of sensitive receptors, and assessment of environmental receptors. Conclusion: In this study, we suggested manners to increase the utilization of KORA. It is anticipated that the further research suggested in the study could contribute to the stabilization of the KORA system.

The Role of Negative-Pressure Wound Therapy in Latissimus Dorsi Flap Donor Site Seroma Prevention: A Cohort Study

  • Angspatt, Apichai;Laopiyasakul, Thana;Pungrasmi, Pornthep;Suwajo, Poonpissamai
    • Archives of Plastic Surgery
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    • v.44 no.4
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    • pp.308-312
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    • 2017
  • Background Donor site seroma is the most common complication after latissimus dorsi (LD) flap harvest. This study aimed to evaluate the efficacy of negative-pressure wound therapy (NPWT) in preventing donor site seroma formation after the harvest of an LD flap for breast reconstruction. Methods In this prospective matched-pair study, 40 patients in whom an LD flap was harvested for breast reconstruction were enrolled. NPWT was used in 20 patients, and in a control group composed of another 20 patients, the conventional donor site dressing technique was used. Information was collected regarding postoperative complications, the incidence of seroma, total drainage volume, the number of percutaneous seroma aspirations, and the volume aspirated. Results In the NPWT group, the incidence of seroma formation after drain removal was significantly lower than in the control group (15% vs. 70%; odds ratio=0.07; relative risk, 0.24). Both the mean percutaneous aspirated volume (P =0.004) and the number of percutaneous aspirations (P=0.001) were also significantly lower in the NPWT group. There were no significant differences in the total drainage volume or the duration of wound drainage between the NPWT dressing group and the control group (P>0.05). Conclusions This study showed that NPWT is a promising tool for reducing the incidence of seroma formation after removing the drain at the donor site after LD flap harvesting. It is a simple and safe technique.

Various Designs of Gluteal Artery Perforator Flap for Buttock Reconstruction (둔부재건을 위한 천공지피판의 다양한 도안)

  • Hong, Seung Eun;Pyon, Jai Kyong
    • Archives of Plastic Surgery
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    • v.34 no.2
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    • pp.197-202
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    • 2007
  • Purpose: The gluteal artery perforator flaps earned its popularity in buttock reconstruction due to the lower morbidity of the donor site and the flexibility in the design. Speedy and safe reconstruction is important for the success of buttock reconstruction. If a proper design is selected, satisfactory results can be obtained with more simple method of surgery. Methods: Between April 2005 and April 2006, buttock reconstruction by using gluteal artery perforator flaps were performed on sacral sores(6 cases), ischial sores(2 cases) and malignant melanoma on buttock(1 case). Various designs depending on the location and the size of the defect was made. In those designs, perforator was used as an axis for the minimal dissection of the vessel. Donor site from which sufficient amount of soft tissue can be transferred was selected, and also not causing high tension against the recipient site during the donor site closure. In addition, postoperative aesthetics, and the possibility of another design of a second operation which can be necessary in the future, was considered. Results: Patient follow up was for a mean period of 10.8 months. All flaps survived except for one that had undergone partial necrosis. Wound dehiscence was observed in one patient treated by secondary closure. Most patients presented with cosmetically and functionally satisfying results Conclusion: By designing the flap using the perforator as an axis, depending on the defect size and degree, reconstruction can be performed with only a small tension to the donor and the recipient site. And the minimal perforator dissection allowed easier and faster reconstruction. Selection of a proper design is the key procedure which greatly affects operation time and result success.