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dc.contributor.authorOtwoma, David
dc.date.accessioned2013-05-04T09:54:41Z
dc.date.available2013-05-04T09:54:41Z
dc.date.issued2000
dc.identifier.urihttp://erepository.uonbi.ac.ke:8080/xmlui/handle/123456789/18979
dc.descriptionMaster of Science, Institute of Nuclear Scienceen
dc.description.abstractMeasurement of the external gamma radiation was done at various radiological facilities in Nairobi using readily available field survey technique and instruments. Film badges were placed at various places where man made radiation sources are used and also where none other than the normal background radiation is present. After periods varying from two days and extending up to two months of continuously monitoring for ambient gamma radiation the films were processed and analyzed for dose recorded on them. Performance checks and stability evaluations were done for equipment used to measure exposure during calibration exercises for selected control films which were exposed to known radiation. Radiation exposure for various occupational categories was estimated in particular those of radiographers working at Kenyatta National Hospitals' Radiotherapy and X-ray Departments, physicists and technicians working at the Physics Section of Materials Testing and Research Laboratories' and also researchers and technicians working at the Institute of Nuclear Science. The deduced exposure was converted to dose using conversion factors available in relevant references and data obtained from measurements of radiation beams using dosimetry instruments. Data obtained showed that the doses received by radiographers and other personnel of Kenyatta National Hospital were the least as they averaged at 0.4 millrSievert (mSv) per month, This was as expected considering the x-ray equipment and the radiotherapy sources are built in radiological safe structures. In contrast the dose rates on the surface and I meter distance from 200 liter drums, containing spent sealed sources of radioactive materials could result in an individual receiving as high as 10 mSv per year. The latter used to be accessible to staff involved with radiation work as well as members of the public since the drums were stored in the open air within the compound. Many radiation workers are not monitored for occupational exposure. This was found to be the case among the least enlightened group of workers such as those found in industry but also researchers and technicians who were well versed in radiation protection principles. The dose received by the exposed personnel at the Institute ofNuc1ear Science was found to vary considerably depending on what type of sources are in use and also how frequently they were used. In one month it would have been possible for a researcher or technician working up to eight hours a day to receive more than 5 mSv but when the workload was low one would receive less than I mSv. Results of cross checking the reliability of ionizing chambers and electrometer belonging to the Radiation Protection Board by comparing them to those of the International Atomic Energy Agency and Radiotherapy Department ofKenyatta National Hospital are presented. The ion chambers, electrometers, cobalt source gamma beam and dose rate meter did not give values which deviated outside measurement uncertainties during the whole study period. In particular, the ion chambers were stable and the values obtained when comparing the calculated dose to that they measured shows the accuracy was less than the upper limit of deviation (± 5%) allowed for radiotherapy work. The stability of the dose rate output from the cobalt teletherapy unit also gave a dosimetry accuracy of better than ±5%. One main limiting observation on film badge use was that in humid conditions noted for some months, the films were not reliable when left for periods exceeding one month in environments modified by man made radiation. Also for cases where an appreciable dose was recorded, especially a single dose above 10 mSv, they could not be evaluated reliably since the deviation would be as high as ± 100% between any two films placed at the same site and presumably had received the same dose. Also for values below 0.4 mSv the film badges could not really distinguish the dose received since this bordered on their detection limit. Despite these shortcomings, the use of film badge dosimetry for measurement of radiation exposure would offer assurance that workers are or are not being over exposed when working in environments modified by man made radiation.en
dc.language.isoenen
dc.titleMonitoring of enviroments modified by man made radiation using film badgeen
dc.typeThesisen
local.publisherFaculty of Engineering, University of Nairobi.en


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