Background: The purpose of this study is to analyze the types of complications, the incidences of complications, and preoperative and postoperative risk factors affecting the incidence of the complication. Material and Method: Between August 1990 and August 1997 in Asan Medical Center, 42 patients(24 men and 18 women) underwent surgical resection for pulmonary aspergilloma. The mean age was 46.6${\pm}$11.5 years(range 29 to 69 years). Hemoptysis(90%) was the most common presentation. Pulmonary tuberculosis was the most common predisposing cause(81%). The associated diseases were bronchiectasis(n=11), active puolmonary tuberculosis(n=9), diabetes mellitus(n=8), lung carcinoid(n=1), and acute myeloblastic leukemia(n=1). Lobectomy was done in 32 cases(76%), segmentectomy or wedge resection in 4, pneumonectomy in 2, and lobectomy combined with segmentectomy in 4. Result: Operative mortality was 2%. The most common postoperative complication was persistent air leakage(n=6). The variables such as age, sex, pulmonary function test, amount and duration of hemoptysis, associated diseases(diabetes mellitus, active pulmonary tuberculosis), mode of preoperative management(steroid, antifungal agent, bronchial arterial embolization), and modes of operative procedures were statistically insignificant. The radiologic extent of infiltration to normal lung parenchyme was statistically significant(p=0.04). Conclusion: We conclude that the extent of the infiltration to normal lung parenchyme in preoperative radiologic studies should be carefully evaluated to reduce the postoperative complications in surgery for pulmonary aspergilloma.
In this study, the exposure amount of IASCC test worker was evaluated by applying the process simulation technology. Using DELMIA Version 5, a commercial process simulation code, IASCC test facility, hot cells, and workers were prepared, and IASCC test activities were implemented, and the cumulative exposure of workers passing through the dose-distributed space could be evaluated through user coding. In order to simulate behavior of workers, human manikins with a degree of freedom of 200 or more imitating the human musculoskeletal system were applied. In order to calculate the worker's exposure, the coordinates, start time, and retention period for each posture were extracted by accessing the sub-information of the human manikin task, and the cumulative exposure was calculated by multiplying the spatial dose value by the posture retention time. The spatial dose for the exposure evaluation was calculated using MCNP6 Version 1.0, and the calculated spatial dose was embedded into the process simulation domain. As a result of comparing and analyzing the results of exposure evaluation by process simulation and typical exposure evaluation, the annual exposure to daily test work in the regular entrance was predicted at similar levels, 0.388 mSv/year and 1.334 mSv/year, respectively. Exposure assessment was also performed on special tasks performed in areas with high spatial doses, and tasks with high exposure could be easily identified, and work improvement plans could be derived intuitively through human manikin posture and spatial dose visualization of the tasks.
Gamma irradiation as a new physical treatment was applied to comparative investigates with a conventional ethylene oxide fumigant on the microbiological and physicochemical qualities of selected spices and dry vegetables such as powdered red pepper, black pepper, welsh onion, onion, garlic, carrot, korean cabbage and instant ramyon soup. The microorganisms contaminated in the sample, including total viable count, thermophilic bacteria, aerobic spore and fungi counts between the $10^4\;to\;10^6/g$ range. Coliforms were found only in black pepper and welsh onion powder as the $10^2\;to\;10^3/g$ level. A radiation dose of 7 to 10 KGy were sterilized completely to the contaminated microorganisms, while ehthylene oxide (E.O.) fumigation reduced of them to the $10^3/g$ level. An optimum dose of irradiation was less detrimental than E.O. fumigation to the physicochemical properties of the sample. Sensory evaluation after three months of storage at room temperatures showed that the overall acceptability of irradiated sample was higher than that of the non treated control as well as E.O. fumigated samples. Comparison gamma irradiation with E.O. gas treatment showed that E.O. treatment was less effective than radiation in cotrolling microbial contamination of spices and vegetables.
Purpose: Those who access to the nuclear medicine department are classified as radiation workers, temporarily access group, and occasional access group as defined by the atomic energy law. The radiation workers and temporarily access people wear a personal radiation dosimeter for checking their own radiation absorbed dose periodically. However, because of the sanitation workers, classified as temporarily access group, who are working in the nuclear medicine department are moved in a cycle with other departments and their works are changeful, it is hard to control their radiation absorbed dose. Thus, this study is going to examine the state of the sanitation worker's radiation absorbed dose, and then make sure whether they are classified as temporarily access group or not. Materials and methods: In the first instance, the first sanitation worker who works in vitro laboratory and PET room and the second sanitation worker who works in gamma camera rooms (invivo room) wore radiation dosimeter-OSL(Optically Stimulated Luminescence)- to measure their own radiation absorbed dose during work time from May to June 2011. Secondly, this study was taken place 5 places in gamma camera rooms, 2 places in PET bed room, operating room, waiting room and cyclotron room in PET and 4 places in vitro laboratory. And then to measure the radiation space dose rate, it is measured 10 times each of places as sanitation worker's work flow by using radiation survey meter. Results: The radiation absorbed dose on OSL of the first c who works in vitro laboratory and PET room and the second one who works in gamma camera rooms are 0.04, 0.02 mSv per month respectively. That means the estimated annual radiation absorbed doses are less than 1mSv as 0.48, 0.24 mSv/yr respectively. The radiation space dose rates as sanitation worker's work flow using survey meter are 0.0037, 0.0019 mSv/day, so the estimated annual radiation absorbed dose are 0.93, 0.47 mSv/yr respectively. The weighted exposure dose of first sanitation worker of each places are 1.62% in cyclotron room, 3.88% in waiting room, 2.39% in operating room, 81.01% in bed room of PET and 11.01% in vitro laboratory. The weighted exposure dose of second sanitation worker of each places are 45.22% in radiopharmaceutical laboratory, gamma 30.64% in camera rooms, 15.65% in waiting room, 8.49% in reading room. Conclusion: The annual radiation absorbed doses on OSL of both sanitation workers are less than 1 mSv per year and the annual radiation absorbed doses by using survey meter are less than 1mSv either, but close up to 1 mSv. Thus, to clarify whether the sanitation workers are temporarily access group or not, and to be lessen their s radiation absorbed dose, they should be educated about management of radiation and modified their work flow or work time appropriately, their radiation absorbed dose would be lessen certainly.
Purpose: In the Nuclear Medicine department of Asan Medical Center, radioactive waste has been disposed of by using several disposal boxes designed for nuclear waste. However, some quantity of radioactivity has been detected occasionally due to some radiologists' carelessness not only from radioactive waste, but also from medical waste such as uncontrolled radioactive waste related to patients, poly gloves or saline solution bottles from radiopharmaceuticals laboratory. Thus, this study is going to suggest a solution to maintain the medical wastes made from controlled areas that can be below maximum permissible surface dose limits by finding the cause of radioactive contamination. Materials and methods: This study was taken place in 17 different places-2 medical wastebaskets in the waiting room, 2 medical wastebaskets in the PET room, 5 medical wastebaskets in the in vitro laboratory and 6 medical wastebaskets in the radiopharmaceuticals laboratory of the East building, 2 medical wastebaskets in the waiting room of the New building of Nuclear Medicine Department in Asan Medical Center from April to August 2010. Mean radioactivity and its standard deviation of each place have been found by measuring surface contamination of medical wastebaskets and backgrounds twice a week, totaling 30 times. An independent t-test of SPSS (Ver. 12.0) statistic program has been used for statistical analysis. Swabs, saline solution bottles and poly gloves collected from each place also measured 30 times, respectively. Results: This study analyzed medical waste and the backgrounds of each place by using survey meter detectors that significant differences of five places did not exist, but existed statistically in twelve places (p<0.05). Also, swabs, saline solution bottles and poly gloves collected from each radioactive waste partly exceed the legal dose limit as a result of measuring by a gamma counter. Conclusion: Backgrounds and the surface doses of radioactive disposal box in all 17 places measured by the survey meter did not exceed the legal dose limit; however, it obviously showed that there were prominent differences in 12 places. Assuming that the cause of the differences was swabs, saline solution bottles and gloves, we examined them by gamma counter, and the results showed remarkably high doses of radioactivity. Consequently, swabs and poly gloves which are normally disposed in the general medical waste box should be disposed in the radioactive waste box furnished by radiopharmaceuticals laboratory. Also, saline solution discharged from radioactive pharmaceutical places is considered as radioactive liquid waste so that it should be disposed of by the septic tank specifically designed for radioactive liquid.
This study is performed in the intervention unit, during interventional procedures and in accordance with the direction and distance during the exposure indoor space is to measure the dose. I was classified at an angle of $45^{\circ}$ counterclockwise from the phantom. Seven(A, B, C, D, E, F, G) were classified as direction. Length was measured from the center of the phantom. Each direction 50cm, 100cm, 150cm, 200cm were classified. I was analyzed by measuring of frontal, lateral, Bi-plan fluoroscopic Spatial dose rate in all 28 points. Measured dose was the highest at 50cm and over 200cm, dose was rapidly decreasing as increased distance. Dose was different more than nine times depending on the distance and direction, Installation of shielding wall can reduce exposure about 84.52% to 93.54%.
Kim, Seon Woong;Kim, In Seek;Park, Dong Hi;No, Tae Mook;Joeng, Jae Kwon;Jung, Seung Wook;Kim, Yeon Jae;Lee, Byung Ki
Tuberculosis and Respiratory Diseases
/
v.56
no.5
/
pp.495-504
/
2004
Background : Bronchial anthracofibrosis is one of the main manifestations of lung disease that is related to woodsmoke inhalation, and it is frequently associated with various pulmonary diseases, such as tuberculosis. The purpose of this study was to evaluate the clinical significance of bronchial anthracofibrosis in patients with endobronchial tuberculosis. Methods : 63 patients, who were diagnosed with endobronchial tuberculosis using bronchoscopy, were included in this study. The patients consisted of 12 males and 51 females, having mean age of 59.5 years. The clinical features, radiologic and bronchoscopic findings between the patients with (37) and without (26) bronchial anthracofibrosis were analyzed retrospectively. Results : When the patients were older, bronchial anthracofibrosis was more frequent. The endobronchial tuberculosis, which was located at the right middle lobal bronchus, was more frequent in the patients with bronchial anthracofibrosis than in the patients without bronchial anthracofibrosis. In the morphologic types of endobronchial tuberculosis, patients with bronchial anthracofibrosis had more edematous-hyperemic and ulcerative types, while patients without bronchial anthracofibrosis had more active caseating. Conclusion : These findings suggest that the presence of bronchial anthracofibrosis can possibly influence the locations and morphologic types of endobronchial tuberculosis.
Journal of the Korea Academia-Industrial cooperation Society
/
v.15
no.6
/
pp.3658-3666
/
2014
The presence of $^{238}U$, $^{232}Th$ and $^{40}K$, which are naturally residing radionuclides, in the ordinary soil of Busan, the 2nd largest city in Korea, was anlayzed and the residents' radiation exposure to ordinary soil was evaluated. Regarding the measurement methods, to conduct a detailed analysis of the naturally residing radionuclides in the soil of Busan, this study divided the 16 administrative districts into a lattice structure with 3 spots, and collected a total of 48 soil samples (July 2012 and April 2013). ICP-MS was used to analyze the concentration of the radioactivity of $^{238}U$ and $^{232}Th$ in the soil, and a HpGe detector, a gamma ray detector, was used to analyze the radioactivity of $^{40}K$. The measurement values of this study were compared with the concentration of radioactivity of East Asian regions. The concentration of $^{238}U$ nuclides in Korea was lower than the mean, whereas the concentration of $^{232}Th$ and $^{40}K$ nuclides was higher than the mean. The higher mean concentrations of $^{232}Th$ and $^{40}K$ than the mean were attributed to the many granite areas that contain a great deal of naturally occurring radionuclides.
Bafckground: Thr role and indication of surgery in the treatment of small cell lung cancer(SCLC) is currently limited and unsettled. Material and Method: We analyzed the surgical results of 9 patients with SCLC at Yosei Medical Center from January 1990 to December 1996. There were 8 males and 1 female, and their mean age was 57.2 years (range; 35-76). Preoperatively SCLC was confirmed in 5, but the other 4 cases were diagnosed as undifferentiated squamous cell carcinoma. All patients underwent pulmoinary resection(lobectomy;5, lobectomy, segmentectomy and en-bloc resection of rib;1, bilobectomy; 2, pneumonectomy;1) and mediastinal lymph node dissection. Results: There were no operative mortality with two complications(postoperative bleeding;1, arrhythmia;1). All cases were diagnosed as SCLC histologically and their TNM staging were confirmed as follows: T1N0M0;1, T2N0M0;4, T3N0M0;1, T3N1M0;1, T2N2M0; 1, T4N0M0;1. All patients had received postoperative chemotherapy, and radiotherapy was combined in 4 patients. During follow up period(range 1-63 months; mean 33.0months), there was only one metastasis to pelvic bone among 8 patients without lymph node metastasis, and all patients were alive. On the other hand, among 3 patients who had regional and/or mediastinal lymph node metastasis or T4 lesion, all patients had recurrences(local;2, brain;1), and 2 patients died. Conclusion: We suggest that the use of TNM staging is beneficial, and surgical resection should be recommended in the patients with early staged SCLC as an important treatment modality.
XOQ_DW code is currently used to assess the atmospheric dispersion fur the routine releases of radioactive gaseous effluents at Yonggwang nuclear power plants. This code was developed based on XOQDOQ code and an additional code is required to assess the atmospheric dispersion for potential accidental releases. In order to assess the atmospheric dispersion fer the accidental releases, XOQAR code has been developed by using PAVAN code that is based on Reg. Guide 1.145. The terrain data of XOQ_DW code inputs and the relative concentrations (X/Q) of XOQ_DW code outputs are used as the inputs of the XOQAR code through the interface with XOQ_DW code. By using this code, the maximum values of X/Q at exclusion area and low population zone boundaries except for sea areas were assessed as $1.33{\times}10^{-4}$ and $7.66{\times}10^{-6}$ sec/$m^3$, respectively. Through the development of this code, a rode system is prepared for assessing the atmospheric dispersion for the accidental releases as well as the routine releases. This developed code ran be used for other domestic nuclear power plants by modifying the terrain input data.
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