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1.
Radiat Prot Dosimetry ; 185(3): 351-354, 2019 Dec 31.
Artículo en Inglés | MEDLINE | ID: mdl-30824922

RESUMEN

Preliminary studies on effective and eye lens doses of six Radiologists, four Cardiologists have been conducted for a period of 3 months. Electronic dosemeters positioned under and over lead apron of staff were used for the dosimetry. The estimated effective dose per month to Cardiologist and Radiologist were 0.01-0.07 mSv and 0.03-0.14 mSv, respectively. The estimated eye lens doses per month to Cardiologists and Radiologists were also 0.15-0.30 mSv and 0.53-3.39 mSv, respectively. The effective doses per month to staff were below the ICRP acceptable limit of 1.67 mSv/month but the upper limit of the range of estimated eye lens dose exceeded the ICRP acceptable limit by a factor of 2. Regular use of protective goggles and consistent eye lens dose monitoring is encouraged at the hospital for dose optimization.


Asunto(s)
Fluoroscopía/métodos , Cristalino/efectos de la radiación , Exposición Profesional/análisis , Personal de Hospital/estadística & datos numéricos , Exposición a la Radiación/análisis , Protección Radiológica/normas , Radiometría/métodos , Cardiología/normas , Dispositivos de Protección de los Ojos , Hospitales de Enseñanza , Humanos , Ropa de Protección/normas , Dosis de Radiación , Radiología/normas
2.
Radiat Prot Dosimetry ; 155(4): 423-31, 2013 Aug.
Artículo en Inglés | MEDLINE | ID: mdl-23419904

RESUMEN

The structural shielding thicknesses of the walls of four computed tomography (CT) facilities in Ghana were re-evaluated to verify the shielding integrity using the new shielding design methods recommended by the National Council on Radiological Protection and Measurements (NCRP). The shielding thickness obtained ranged from 120 to 155 mm using default DLP values proposed by the European Commission and 110 to 168 mm using derived DLP values from the four CT manufacturers. These values are within the accepted standard concrete wall thickness ranging from 102 to 152 mm prescribed by the NCRP. The ultrasonic pulse testing of all walls indicated that these are of good quality and free of voids since pulse velocities estimated were within the range of 3.496±0.005 km s(-1). An average dose equivalent rate estimated for supervised areas is 3.4±0.27 µSv week(-1) and that for the controlled area is 18.0±0.15 µSv week(-1), which are within acceptable values.


Asunto(s)
Equipos de Seguridad , Protección Radiológica/instrumentación , Tomografía Computarizada por Rayos X/instrumentación , Calibración , Materiales de Construcción , Diseño de Equipo , Arquitectura y Construcción de Instituciones de Salud , Ghana , Hospitales , Dosis de Radiación , Protección Radiológica/métodos , Ultrasonido
3.
Radiat Prot Dosimetry ; 150(3): 350-8, 2012 Jul.
Artículo en Inglés | MEDLINE | ID: mdl-22021059

RESUMEN

Institutions in the education, research and industrial sectors in Ghana are quite few in comparison to the medical sector. Occupational exposure to radiation in the education, research and industrial sectors in Ghana have been analysed for a 10 y period between 2000 and 2009, by extracting dose data from the database of the Radiation Protection Institute, Ghana Atomic Energy Commission. Thirty-four institutions belonging to the three sectors were monitored out of which ∼65% were in the industrial sector. During the 10 y study period, monitored institutions ranged from 18 to 23 while the exposed workers ranged from 246 to 156 between 2000 and 2009. Annual collective doses received by all the exposed workers reduced by a factor of 2 between 2000 and 2009. This is seen as a reduction in annual collective doses in education/research and industrial sectors by ∼39 and ∼62%, respectively, for the 10 y period. Highest and least annual collective doses of 182.0 man mSv and 68.5 man mSv were all recorded in the industrial sector in 2000 and 2009, respectively. Annual average values for dose per institution and dose per exposed worker decreased by 49 and 42.9%, respectively, between 2000 and 2009. Average dose per exposed worker for the 10 y period was least in the industrial sector and highest in the education/research sector with values 0.6 and 3.7 mSv, respectively. The mean of the ratio of annual occupationally exposed worker (OEW) doses for the industrial sector to the annual OEW doses for the education/research sector was 0.67, a suggestion that radiation protection practices are better in the industrial sector than they are in the education/research sector. Range of institutional average effective doses within the education/research and industrial sectors were 0.059-6.029, and 0.110-2.945 mSv, respectively. An average dose per all three sectors of 11.87 mSv and an average dose per exposed worker of 1.12 mSv were realised for the entire study period. The entire study period had 187 instances in which exposed workers received individual annual doses >1 mSv, with exposed workers in the education/research sector primarily receiving most of this individual dose.


Asunto(s)
Exposición Profesional/análisis , Monitoreo de Radiación , Radiación Ionizante , Recuento Corporal Total , Centros Médicos Académicos , Investigación Biomédica , Femenino , Ghana , Humanos , Industrias , Masculino , Dosis de Radiación , Dosimetría Termoluminiscente
4.
Radiat Prot Dosimetry ; 142(2-4): 88-91, 2010 Dec.
Artículo en Inglés | MEDLINE | ID: mdl-20699247

RESUMEN

The safety culture of selected practices and facilities in Ghana utilising radiation sources or radiation emitting devices has been assessed using a performance indicator, which provided status information on management and operating staff commitment to safety. The questionnaire was based on the following broad areas: general safety considerations, safety policy at the facility level, safety practices at the facility level, definition of responsibility, staff training, safety of the physical structure of the facility and the emergency plans. The analysis showed that the percentage levels of commitment to safety for the respective practices are as follows: conventional radiography, 23.3-90.0%; research reactor, 73.3%; gamma irradiation facility, 53.3%; radiotherapy, 76.7%; X-ray scanner, 80.0%; gamma scanner, 76.7%; industrial radiography 86.7% and nuclear density practice, 78%. None of the practices or facilities was able to satisfy all the requirements that will ensure a 100% level of safety culture.


Asunto(s)
Protección Radiológica/normas , Radiación Ionizante , Liberación de Radiactividad Peligrosa/prevención & control , Servicio de Radiología en Hospital/normas , Administración de la Seguridad , Cultura , Ghana , Humanos , Encuestas y Cuestionarios
5.
Radiat Prot Dosimetry ; 136(3): 203-8, 2009 Sep.
Artículo en Inglés | MEDLINE | ID: mdl-19770212

RESUMEN

Organ and effective doses to 90 patients undergoing some selected fluoroscopic examinations at the Korle-Bu Teaching Hospital were estimated using the Monte Carlo-based program (PCXMC version 1.5). Radiation dose was estimated from free-in-air measurements. The mean effective doses were found to be 0.29 +/- 0.07, 0.84 +/- 0.13, 3.15 +/- 0.44, 6.24 +/- 0.70 and 0.38 +/- 0.05 mSv for urethrogram, barium swallow, barium meal, barium enema and myelogram examinations, respectively. The dose area product was estimated to be 3.55 +/- 0.95, 16.44 +/- 2.60, 50.81 +/- 7.04, 99.69 +/- 10.85 and 9.32 +/- 0.99 Gy cm(2) for urethrogram, barium swallow, barium meal, barium enema and myelogram examinations, respectively. Optimisation of procedures is required for barium enema and barium meal examinations.


Asunto(s)
Carga Corporal (Radioterapia) , Exposición a Riesgos Ambientales/análisis , Fluoroscopía/estadística & datos numéricos , Recuento Corporal Total/estadística & datos numéricos , Ghana/epidemiología , Humanos , Dosis de Radiación , Medición de Riesgo
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