Purpose: This study aims to systematically analyze the radioactive waste generated from treatments using radioactive Iodine-131 (I-131), Lutetium-177 (Lu-177), and Actinium-225 (Ac-225) to facilitate safe waste management practices. Methods: I-131 is primarily used in thyroid cancer treatment, while Lu-177 and Ac-225 are used to treat prostate cancer. Radioactive waste generated after these treatments was collected from patients at the Korea Cancer Center Hospital and categorized into clothing, slippers, syringes, and other items. The radioactivity concentration of each item was measured using a calibrated highpurity germanium detector. Using measurements, the self-disposal date of each waste item was calculated according to the permissible disposal levels defined by the Nuclear Safety and Security Commission (NSSC) under domestic nuclear safety regulations. Results: For the I-131 radioactive waste, clothing, towels, and tableware exhibited high radioactivity concentrations, with most items exceeding the permissible self-disposal levels.Conversely, the type and quantity of waste generated from Lu-177 and Ac-225 that were intravenously injected were relatively minimal, with certain items below the self-disposal thresholds, enabling immediate disposal. For Ac-225, no permissible self-disposal concentration is specified by the NSSC, unlike other therapeutic nuclides. Hence, additional studies are required to establish clear guidelines. Conclusions These findings provide valuable data for optimizing radioactive waste management, potentially reducing disposal time and costs, minimizing radiation exposure, and enhancing hospital safety practices.

Purpose: This study aims to systematically analyze the radioactive waste generated from treatments using radioactive Iodine-131 (I-131), Lutetium-177 (Lu-177), and Actinium-225 (Ac-225) to facilitate safe waste management practices. Methods: I-131 is primarily used in thyroid cancer treatment, while Lu-177 and Ac-225 are used to treat prostate cancer. Radioactive waste generated after these treatments was collected from patients at the Korea Cancer Center Hospital and categorized into clothing, slippers, syringes, and other items. The radioactivity concentration of each item was measured using a calibrated highpurity germanium detector. Using measurements, the self-disposal date of each waste item was calculated according to the permissible disposal levels defined by the Nuclear Safety and Security Commission (NSSC) under domestic nuclear safety regulations. Results: For the I-131 radioactive waste, clothing, towels, and tableware exhibited high radioactivity concentrations, with most items exceeding the permissible self-disposal levels.Conversely, the type and quantity of waste generated from Lu-177 and Ac-225 that were intravenously injected were relatively minimal, with certain items below the self-disposal thresholds, enabling immediate disposal. For Ac-225, no permissible self-disposal concentration is specified by the NSSC, unlike other therapeutic nuclides. Hence, additional studies are required to establish clear guidelines. Conclusions These findings provide valuable data for optimizing radioactive waste management, potentially reducing disposal time and costs, minimizing radiation exposure, and enhancing hospital safety practices.

Purpose: This study aims to systematically analyze the radioactive waste generated from treatments using radioactive Iodine-131 (I-131), Lutetium-177 (Lu-177), and Actinium-225 (Ac-225) to facilitate safe waste management practices. Methods: I-131 is primarily used in thyroid cancer treatment, while Lu-177 and Ac-225 are used to treat prostate cancer. Radioactive waste generated after these treatments was collected from patients at the Korea Cancer Center Hospital and categorized into clothing, slippers, syringes, and other items. The radioactivity concentration of each item was measured using a calibrated highpurity germanium detector. Using measurements, the self-disposal date of each waste item was calculated according to the permissible disposal levels defined by the Nuclear Safety and Security Commission (NSSC) under domestic nuclear safety regulations. Results: For the I-131 radioactive waste, clothing, towels, and tableware exhibited high radioactivity concentrations, with most items exceeding the permissible self-disposal levels.Conversely, the type and quantity of waste generated from Lu-177 and Ac-225 that were intravenously injected were relatively minimal, with certain items below the self-disposal thresholds, enabling immediate disposal. For Ac-225, no permissible self-disposal concentration is specified by the NSSC, unlike other therapeutic nuclides. Hence, additional studies are required to establish clear guidelines. Conclusions These findings provide valuable data for optimizing radioactive waste management, potentially reducing disposal time and costs, minimizing radiation exposure, and enhancing hospital safety practices.

Background: Oral sulfate tablets (OSTs) are bowel preparation agents that combine oral sulfate solution and simethicone. This study compared the efficacy, tolerability, and safety of OST compared to 2 L-polyethylene glycol plus ascorbic acid (2 L-PEG/ASC). Methods: This prospective, randomized, controlled, single-blinded, multicenter, noninferiority trial enrolled 211 healthy adults who underwent colonoscopy between May 2020 and September 2022 at 13 university hospitals. The bowel cleansing rate was assessed using the Boston Bowel Preparation Scale (BBPS) and Harefield Cleansing Scale (HCS), and the preparation agents were administered in split regimens. Results: The total BBPS score (8.2 ± 1.5 vs. 7.8 ± 1.4, p = 0.040) and the high-quality bowel cleansing rates in the right colon (73.2% vs. 50.5), transverse colon (80.6% vs. 68.0%), and left colon (81.5% vs. 67.0%) on the BBPS were significantly higher in the OST group than in the 2 L-PEG/ASC group. However, the rates of successful cleansing according to BBPS (90.7% vs. 91.2%) and HCS (96.3% vs. 94.2%) did not significantly differ between the two groups.The taste, ease, and amount of consumption of the preparation agent; and willingness to repeat colonoscopy with the same agent (89.8% vs. 78.6%, P = 0.026) were significantly better in the OST group compared to the 2 L-PEG/ASC group. Adverse events and clinically significant laboratory changes were not significantly different between the two groups. Conclusion The OST was not inferior to 2 L-PEG/ASC in terms of bowel cleansing efficacy and showed better tolerability when used for bowel preparation for colonoscopy.

Background: Oral sulfate tablets (OSTs) are bowel preparation agents that combine oral sulfate solution and simethicone. This study compared the efficacy, tolerability, and safety of OST compared to 2 L-polyethylene glycol plus ascorbic acid (2 L-PEG/ASC). Methods: This prospective, randomized, controlled, single-blinded, multicenter, noninferiority trial enrolled 211 healthy adults who underwent colonoscopy between May 2020 and September 2022 at 13 university hospitals. The bowel cleansing rate was assessed using the Boston Bowel Preparation Scale (BBPS) and Harefield Cleansing Scale (HCS), and the preparation agents were administered in split regimens. Results: The total BBPS score (8.2 ± 1.5 vs. 7.8 ± 1.4, p = 0.040) and the high-quality bowel cleansing rates in the right colon (73.2% vs. 50.5), transverse colon (80.6% vs. 68.0%), and left colon (81.5% vs. 67.0%) on the BBPS were significantly higher in the OST group than in the 2 L-PEG/ASC group. However, the rates of successful cleansing according to BBPS (90.7% vs. 91.2%) and HCS (96.3% vs. 94.2%) did not significantly differ between the two groups.The taste, ease, and amount of consumption of the preparation agent; and willingness to repeat colonoscopy with the same agent (89.8% vs. 78.6%, P = 0.026) were significantly better in the OST group compared to the 2 L-PEG/ASC group. Adverse events and clinically significant laboratory changes were not significantly different between the two groups. Conclusion The OST was not inferior to 2 L-PEG/ASC in terms of bowel cleansing efficacy and showed better tolerability when used for bowel preparation for colonoscopy.

Background: Oral sulfate tablets (OSTs) are bowel preparation agents that combine oral sulfate solution and simethicone. This study compared the efficacy, tolerability, and safety of OST compared to 2 L-polyethylene glycol plus ascorbic acid (2 L-PEG/ASC). Methods: This prospective, randomized, controlled, single-blinded, multicenter, noninferiority trial enrolled 211 healthy adults who underwent colonoscopy between May 2020 and September 2022 at 13 university hospitals. The bowel cleansing rate was assessed using the Boston Bowel Preparation Scale (BBPS) and Harefield Cleansing Scale (HCS), and the preparation agents were administered in split regimens. Results: The total BBPS score (8.2 ± 1.5 vs. 7.8 ± 1.4, p = 0.040) and the high-quality bowel cleansing rates in the right colon (73.2% vs. 50.5), transverse colon (80.6% vs. 68.0%), and left colon (81.5% vs. 67.0%) on the BBPS were significantly higher in the OST group than in the 2 L-PEG/ASC group. However, the rates of successful cleansing according to BBPS (90.7% vs. 91.2%) and HCS (96.3% vs. 94.2%) did not significantly differ between the two groups.The taste, ease, and amount of consumption of the preparation agent; and willingness to repeat colonoscopy with the same agent (89.8% vs. 78.6%, P = 0.026) were significantly better in the OST group compared to the 2 L-PEG/ASC group. Adverse events and clinically significant laboratory changes were not significantly different between the two groups. Conclusion The OST was not inferior to 2 L-PEG/ASC in terms of bowel cleansing efficacy and showed better tolerability when used for bowel preparation for colonoscopy.

Purpose: This study aims to systematically analyze the radioactive waste generated from treatments using radioactive Iodine-131 (I-131), Lutetium-177 (Lu-177), and Actinium-225 (Ac-225) to facilitate safe waste management practices. Methods: I-131 is primarily used in thyroid cancer treatment, while Lu-177 and Ac-225 are used to treat prostate cancer. Radioactive waste generated after these treatments was collected from patients at the Korea Cancer Center Hospital and categorized into clothing, slippers, syringes, and other items. The radioactivity concentration of each item was measured using a calibrated highpurity germanium detector. Using measurements, the self-disposal date of each waste item was calculated according to the permissible disposal levels defined by the Nuclear Safety and Security Commission (NSSC) under domestic nuclear safety regulations. Results: For the I-131 radioactive waste, clothing, towels, and tableware exhibited high radioactivity concentrations, with most items exceeding the permissible self-disposal levels.Conversely, the type and quantity of waste generated from Lu-177 and Ac-225 that were intravenously injected were relatively minimal, with certain items below the self-disposal thresholds, enabling immediate disposal. For Ac-225, no permissible self-disposal concentration is specified by the NSSC, unlike other therapeutic nuclides. Hence, additional studies are required to establish clear guidelines. Conclusions These findings provide valuable data for optimizing radioactive waste management, potentially reducing disposal time and costs, minimizing radiation exposure, and enhancing hospital safety practices.

Background: Oral sulfate tablets (OSTs) are bowel preparation agents that combine oral sulfate solution and simethicone. This study compared the efficacy, tolerability, and safety of OST compared to 2 L-polyethylene glycol plus ascorbic acid (2 L-PEG/ASC). Methods: This prospective, randomized, controlled, single-blinded, multicenter, noninferiority trial enrolled 211 healthy adults who underwent colonoscopy between May 2020 and September 2022 at 13 university hospitals. The bowel cleansing rate was assessed using the Boston Bowel Preparation Scale (BBPS) and Harefield Cleansing Scale (HCS), and the preparation agents were administered in split regimens. Results: The total BBPS score (8.2 ± 1.5 vs. 7.8 ± 1.4, p = 0.040) and the high-quality bowel cleansing rates in the right colon (73.2% vs. 50.5), transverse colon (80.6% vs. 68.0%), and left colon (81.5% vs. 67.0%) on the BBPS were significantly higher in the OST group than in the 2 L-PEG/ASC group. However, the rates of successful cleansing according to BBPS (90.7% vs. 91.2%) and HCS (96.3% vs. 94.2%) did not significantly differ between the two groups.The taste, ease, and amount of consumption of the preparation agent; and willingness to repeat colonoscopy with the same agent (89.8% vs. 78.6%, P = 0.026) were significantly better in the OST group compared to the 2 L-PEG/ASC group. Adverse events and clinically significant laboratory changes were not significantly different between the two groups. Conclusion The OST was not inferior to 2 L-PEG/ASC in terms of bowel cleansing efficacy and showed better tolerability when used for bowel preparation for colonoscopy.

Purpose: This study aims to systematically analyze the radioactive waste generated from treatments using radioactive Iodine-131 (I-131), Lutetium-177 (Lu-177), and Actinium-225 (Ac-225) to facilitate safe waste management practices. Methods: I-131 is primarily used in thyroid cancer treatment, while Lu-177 and Ac-225 are used to treat prostate cancer. Radioactive waste generated after these treatments was collected from patients at the Korea Cancer Center Hospital and categorized into clothing, slippers, syringes, and other items. The radioactivity concentration of each item was measured using a calibrated highpurity germanium detector. Using measurements, the self-disposal date of each waste item was calculated according to the permissible disposal levels defined by the Nuclear Safety and Security Commission (NSSC) under domestic nuclear safety regulations. Results: For the I-131 radioactive waste, clothing, towels, and tableware exhibited high radioactivity concentrations, with most items exceeding the permissible self-disposal levels.Conversely, the type and quantity of waste generated from Lu-177 and Ac-225 that were intravenously injected were relatively minimal, with certain items below the self-disposal thresholds, enabling immediate disposal. For Ac-225, no permissible self-disposal concentration is specified by the NSSC, unlike other therapeutic nuclides. Hence, additional studies are required to establish clear guidelines. Conclusions These findings provide valuable data for optimizing radioactive waste management, potentially reducing disposal time and costs, minimizing radiation exposure, and enhancing hospital safety practices.

Background/Aims: Guide tube-assisted endoscopy for procedures that require repeated endoscopic access is safer and more effective than conventional endoscopy. However, its effectiveness has not been confirmed in animal studies. We assessed the usefulness of guide tube-assisted endoscopic procedures in an in vivo porcine model. Methods: Five different guide tube-assisted endoscopic procedures were performed by experienced endoscopists on a pig weighing 32 kg. To evaluate the efficacy of these procedures, we compared the endoscopic approach time when a guide tube was used to that when it was not. Additional endoscopic procedures using a guide tube were performed, including multiple foreign body extractions, multiple polypectomies, and multiple submucosal dissections. To evaluate safety, we compared the insertion force into the proximal esophagus between the guide tube and conventional overtube methods. Results: Using the endoscopic approach with a guide tube required a shorter average approach time to reach the three target lesions than when using the endoscopic approach without a guide tube (p<0.001). Compared to the conventional overtube method, the guide tube method produced a lower average resistance during insertion into the upper esophagus (p<0.001). Conclusions Guide tube-assisted endoscopic procedures are effective and safe for repeated endoscopic access in an in vivo porcine model.