• Title/Summary/Keyword: Medical Waste

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Kinetics for Citric Acid Production from the Concentrated Milk Factory Waste Water by Aspergillus niger ATCC 9142

  • Suh, Myung-Gyo;Roh, Jong-Su;Lee, Kook-Eui;Lee, Yong-Hee;Chung, Kyung-Tae
    • Proceedings of the Korean Environmental Health Society Conference
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    • 2005.06a
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    • pp.359-364
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    • 2005
  • The possible use of milk factory waste water as fermentation media for the production of citric acid by cells of Aspergillus niger ATCC 9142 has been investigated. The addition of $Mn^{2+}$, $Fe^{2+}$ and $Cu^{2+}$ to a medium promoted the citric acid production steadily, but addition of another metal ion $Mg^{2+}$decreased the citric acid production. The concentrations of citric acid were marked up to 7.2g/1 and 16.5g/l in a batch bioreactor by A. niger ATCC 9142 with 50g/1 and 100g/l of reducing sugar concentration in milk factory waste water, respectively.

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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.

Meat Value Chain Losses in Iran

  • Ranaei, Vahid;Pilevar, Zahra;Esfandiari, Changiz;Khaneghah, Amin Mousavi;Dhakal, Rajan;Vargas-Bello-Perez, Einar;Hosseini, Hedayat
    • Food Science of Animal Resources
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    • v.41 no.1
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    • pp.16-33
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    • 2021
  • To stop hunger, reducing food losses is a potential movement towards saving food. A large portion of these losses could be avoided and reduced through the improved food chain in many countries. Raising awareness on how and where food losses occur will help recovering foods such as meat by identifying solutions and convincing people to implement those solutions. This, in turn, will lead to private and public efforts to recover meat that might be otherwise wasted. After highlighting the importance of food saving benefits and relevant statistics, this paper explains the possible ways to reduce meat loss and waste in abattoirs and presents a framework for prevention according to the estimates of meat losses in Iran meat supply. The current article answers the questions of where do we have the meat loss in Iran and what approaches are most successful in reducing losses in the meat industry. The national average loss and waste in meat production are about 300,000 metric tonnes (about 15%). Many segments and players are involved with this huge amount of losses in the meat value chain, a large portion of these losses could be avoided and reduced by about 25% through using by-products with the mechanization of design and manufacturing. The production amount of mechanically deboned meat (MDM) is 105,091,000 kg, concluding the major waste (88.33%) of total poultry losses. Ensuring appropriate actions by exploiting the full potential of engaged Iranian associations and institutes is considered to reduce the losses.

Determination of Self-Disposal date by the Analysis of Radioactive Waste Contamination for 1131I Therapy Ward (131I 치료입원실 폐기물 방사능 오염도 분석 및 자체처분가능일자 산출)

  • Kim, Gi-sub;Jung, Haijo;Park, Min-seok;Jeon, Gjin-seong
    • The Korean Journal of Nuclear Medicine Technology
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    • v.17 no.1
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    • pp.3-6
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    • 2013
  • Purpose: The treatment of thyroid cancer patients was continuously increased. According to the increment of thyroid cancer patients, the establishment of iodine therapy site was also increased in each hospital. This treatment involves the administration of radioactive iodine, which will be given in the form of a capsule. Therefore, protections and managements for radioactive source pollution and radiation exposure should be necessary for radiation safety. Among the many problems, the problem of disposing the radioactive wastes was occurred. In this study, The date for self-disposal for radioactive wastes, which were contaminated in clothes, bedclothes and trash, were calculated. Materials and Methods: The number of iodine therapy ward was 15 in Korea Institute of Radiological Medical and Sciences. Recently, 8 therapy wards were operated for iodine therapy patients and others were on standby for emergency treatment ward of any radiation accidents. Radioactive wastes, which were occurred in therapy ward, were clothes, bedclothes, bath cover for patients washing water and food and drink which was leftover by patients. Each sample was hold into the marinelli beaker (clothes, bedclothes, bath covers) and 90 ml beaker (food, drink, and washing water). The activities of collected samples were measured by HpGe MCA device (Multi Channel Analysis, CANBERRA, USA) Results: The storage period for the each kind of radioactive wastes was calculated by equation of storage periods based on the measurement outcomes. The average storage period was 60 days for the case of clothes, and the maximum storage period was 93 days for patient bottoms. The average storage period and the maximum storage period for the trash were 69 days and 97 days, respectively. The leftover foods and drinks had short storage period (the average storage period was 25 days and maximum storage period was 39 days), compared with other wastes. Conclusion: The proper storage period for disposing the radioactive waste (clothes, bedclothes and bath cover) was 100 days by the regulation on self-disposal of radioactive waste. In addition, the storage period for disposing the liquid radioactive waste was 120 days. The current regulation for radioactive waste self-disposing was not suitable for the circumstances of each radioactive therapy facility. Therefore, it was necessary to reduce the leftover food and drinks by adequate table setting for patients, and improve the process and regulation for disposing the short-half life radioactive wastes.

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A Study on Mercury Emission Factor for Environmental Impact Assessment of Municipal Waste Incinerator (소각장 환경영향평가시 수은 배출 계수에 관한 연구)

  • Chun, Mee-Kyung;Park, Seok-Soon
    • Journal of Environmental Impact Assessment
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    • v.7 no.2
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    • pp.113-125
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    • 1998
  • The amount of mercury emitted from an incinerator depends on the properties of waste, combustion condition, and control devices. Mercury concentration in air proportionates to the increase of incinerator installation. The purpose of this study is to provide a method for determination of mercury emission factor which can predict the amount of mercury emitted from each incinerator specifically. Case study was performed for N municipal waste incinerator. Based on the method presented in this paper, we obtained mercury emission factor as 1.85~1.95 g Hg/t at N Municipal Waste Incinerator and this result was regarded as reasonable when compared with existing mercury emission factor in reference cases. Fluorescent lamps turned out to be the most important source(44.4%) of mercury in municipal waste and its amount will tend to increase, while batteries become less significant. In addition, medical waste is one of the major source of mercury.

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Dental Waste Management Practices at Dental Offices in Gyeongsangnam-do (경남지역 치과의원 의료폐기물 관리실태)

  • Kim, Hae-Jin;SaKong, Joon
    • Journal of Environmental Health Sciences
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    • v.38 no.4
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    • pp.332-339
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    • 2012
  • Objectives: The purpose of this study was to prevent health problems and environmental contamination resulting from inappropriate management of dental wastes and to provide reference data for revision and supplementation of dental clinic waste management guidelines. Methods: From 640 total of dental clinics registered in 16 cities and counties in Gyeongsangnam-do, 100 (60 in Changwon (Masan, Changwon), 29 in Gimhae, and 11 in Jinju) were included in this study. From July 2010 to September 2010, investigators visited the 100 dental clinics and conducted survey interviews using a structured survey questionnaire regarding disposal methods for liquid wastes (suction pump, spittoon container waste, used liquid disinfectants, and X-ray developer), and disposal methods for solid waste (suction pump, spittoon container waste, and general medical waste). Results: All the 100 dental clinics were found to treat liquid waste from suction pumps and spittoon containers in the same manner as general waste water. Nineteen percent of the clinics treated solid waste that was not filtered through the filter of a suction pump as general waste. Fifty or more percent of the clinics treated solid waste in spittoon containers as general waste. Seventy percent of the clinics used disinfectant solution, although most of them treated used disinfectants in the same manner as general waste water. Some clinics treated used X-ray developer and X-ray fixer in the same manner as general waste water. In most of the clinics, used drapes were washed within the clinic. Conclusions: It was found that waste water and dental wastes at some dental clinics were treated in inappropriately. Thus, in conclusion, the development of guidelines regarding proper management of liquid and solid dental waste at dental clinics is required, and hygiene and environmental training for workers at dental clinics is necessary.

Measurement and Estimation for the Clearance of Radioactive Waste Contaminated with Radioisotopes for Medical Application (의료용 방사성폐기물 자체처분을 위한 방사능 측정 및 평가)

  • Kim, Changbum;Park, MinSeok;Kim, Gi-Sub;Jung, Haijo;Jang, Seongjoo
    • Progress in Medical Physics
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    • v.25 no.1
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    • pp.8-14
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    • 2014
  • The amounts of radioactive wastes to be disposed in the medical institute have been increased due to development of radiation diagnosis and therapy rapidly. They are produced mostly by the very short lived radioisotopes such as $^{18}F$ used in PET/CT, $^{99m}Tc$, $^{123}I$, $^{125}I$ and $^{201}Tl$, etc. IAEA proposed a criteria for the clearance level of waste which depends on the individual ($10{\mu}Sv/y$) and collective dose (1 man-Sv/y), and concentration of each nuclide (IAEA Safety Series No 111-P-1.1, 1992 and IAEA RS-G-1.7, 2004). Radioactive wastes of $^{18}F$, $^{99m}Tc$, $^{123}I$, $^{125}I$ and $^{201}TI$ in the several types of container like Marinelli beaker, vial and plastic, were collected to measure the concentration of the waste of each nuclide in accordance with IAEA criteria. The measurement method and procedure of determining specific activity of the wastes using gamma emitters like MCA, gamma counter and beta emitters were developed. For the efficiency calibration of the detectors, CRM (certified reference material) which has the same dimension and shape was provided by Korea Research Institute of Standards and Science (KRISS). Correction factor of the radioactivity decay was calculated based on the measurement results, and the consideration of mutual relation with theoretical equation. The result of this study will be proposed as ISO standard.