RESUMEN
The purpose of this study was to verify the shielding evaluation method for medical X-ray imaging facilities in Report No. 147 of the National Council on Radiation Protection and Measurements (NCRP). We investigated the concept of radiation protection and the major revised point in Report No. 147. The goal of radiation protection in Report No. 147 was compared with that in Japan. Using the data of the Imaging Performance Assessment of CT scanners (ImPACT) 2006 and the latest pre-installation manuals of several manufactures for different computed tomography (CT) scanner models, we verified the shielding method for CT installations. The concept of radiation protection in Report No. 147 was based on the recommendation of the International Commission on Radiological Protection (ICRP) Publication 60. On the shielding method for CT units, compared with the CT scatter fraction for the body phantom in Report No. 147 was approximately 10% less than the results of the computation. In conclusion, we should note the use of the CT scatter fraction for the body phantom provided by Report No. 147; however, it is possible to apply the fundamental concept of the shielding evaluation in Report No. 147 to the shielding evaluation method in Japan.
Asunto(s)
Protección Radiológica/normas , Tomografía Computarizada por Rayos X , Estudios de Evaluación como Asunto , Japón , Fantasmas de Imagen , Protección Radiológica/métodosRESUMEN
We conducted a questionnaire survey about radiation-safety management condition in Japanese nuclear medicine facilities to make materials of proposition for more reasonable management of medical radioactive waste. We distributed a questionnaire to institutions equipped with Nuclear Medicine facilities. Of 1,125 institutions, 642 institutes (52.8%) returned effective answers. The questionnaire covered the following areas: 1) scale of an institution, 2) presence of enforcement of radiotherapy, 3) system of a tank, 4) size and number of each tank, 5) a form of draining-water system, 6) a displacement in a radioactive rays management area, 7) a measurement method of the concentration of medical radioactive waste in draining water system, 8) planned and used quantity of radioisotopes for medical examination and treatment, 9) an average displacement of hospital for one month. In most institutions, a ratio of dose limitation of radioisotope in draining-water system was less than 1.0, defined as an upper limitation in ordinance. In 499 hospitals without facilities of hospitalization for unsealed radioisotope therapy, 473 hospitals reported that sum of ratios of dose limits in a draining-water system was less than 1.0. It was calculated by used dose of radioisotope and monthly displacement from hospital, on the premise that all used radioisotope entered in the general draining-water system. When a drainage including radioactivity from a controlled area join with that from other area before it flows out of a institution, it may be diluted and its radioactive concentration should be less than its upper limitation defined in the rule. Especially, in all institutions with a monthly displacement of more than 25,000 m3, the sum of ratio of the concentration of each radionuclide to the concentration limit dose calculated by used dose of radioisotope, indicated less than 1.0.
Asunto(s)
Medicina Nuclear , Radiación , Residuos Radiactivos , Administración de la Seguridad/normas , Encuestas y Cuestionarios , Humanos , Servicio de Medicina Nuclear en Hospital , Administración de ResiduosRESUMEN
To explore the possibility of which medical radioactive wastes could be disposed as general wastes after keeping them a certain period of time and confirming that their radioactivity reach a background level (BGL), we made a survey of these wastes in several nuclear medicine facilities. The radioactive wastes were collected for one week, packed in a box according to its half-life, and measured its radioactivity by scintillation survey meter with time. Some wastes could reach a BGL within 10 times of half-life, but 19% of the short half-life group (group 1) including 99mTc and 123I, and 8% of the middle half-life group (group 2) including 67Ga, (111)In, and 201Tl did not reach a BGL within 20 times of half-life. A reason for delaying the time of reaching a BGL might be partially attributed to high initial radiation dose rate or heavy package weight. However, mixing with the nuclides of longer half-life was estimated to be the biggest factor affecting this result. When disposing medical radioactive wastes as general wastes, it is necessary to avoid mixing with radionuclide of longer half-life and confirm that it reaches a BGL by actual measurement.