scholarly journals Knowledge and awareness of orthopaedic surgeons about radiation hazards in operation theatres

2021 ◽  
Vol 7 (5) ◽  
pp. 1015
Author(s):  
Manik Sehgal ◽  
Bhanu Awasthi ◽  
Saloni Sood ◽  
Sunil Raina ◽  
Rubinder Kaur ◽  
...  
Keyword(s):  
Soft Tissue ◽  
Minimally Invasive ◽  
Effective Dose ◽  
Annual Effective Dose ◽  
Maximum Amount ◽  
Whole Body ◽  
Medical Professionals ◽  
Radiation Hazards ◽  
Orthopaedic Patients ◽  
Ionising Radiations

<p class="abstract"><strong>Background:</strong> Due to increase in geriatric orthopaedic patients minimally invasive soft tissue and orthopaedic surgeries are gaining. But such procedures have increased the surgeon’s dependence on fluoroscopy which has exposed them to ever increasing dosage of ionising radiations (both direct and scattered).</p><p class="abstract"><strong>Methods:</strong> The study was carried out among medical professionals attending annual north zone conference of orthopaedics using a pre-designed questionnaire on a non-probability sample of 200 orthopedicians.  Questionnaires contained 11 MCQs.<strong></strong></p><p class="abstract"><strong>Results:</strong> 62% of the surgeons believed that hands receive maximum amount of C-arm radiations followed by thyroid (25%). 9% of surgeons have answered eyes and 4% say gonads. 31% of surgeons believe that 100 mSv is allowable annual effective whole-body dose of radiation. 15% believe it to be 500 msv. Majority (37%) of the surgeons had no idea on the allowable annual effective whole-body dose of radiation. 30% of surgeons believe that allowable annual effective dose of radiation for hands is 50 msv. Further 23% of the surgeons believe it to be 100 msv. 50% have no idea about this.</p><p class="abstract"><strong>Conclusions:</strong> All orthopaedic residents and surgeons should have more information and knowledge about ionising radiation. Special courses and workshops can be arranged at local, regional and national levels in this regard.</p><p class="abstract"> </p>

scholarly journals Determination of natural radioactivity, 222Rn and 220Rn exhalation rates and radiation hazards of fly ash and fly ash brick used in Baotou, China

2016 ◽  
Vol 31 (3) ◽  
pp. 282-290 ◽  
Author(s):  
Yuxin Li ◽  
Xinwei Lu ◽  
Xiaolan Zhang
Keyword(s):  
Fly Ash ◽  
Effective Dose ◽  
Natural Radioactivity ◽  
Annual Effective Dose ◽  
Hazard Index ◽  
Radium Equivalent Activity ◽  
Radiation Hazards ◽  
External Hazard Index ◽  
Radium Equivalent ◽  
Local Residents

Natural radioactivity levels, 222Rn and 220Rn exhalation rates and radiation hazards of fly ash and fly ash brick used in Baotou, China were determined. The activity concentrations of 226Ra, 232Th, and 40K in fly ash samples ranged from 38.81 to 93.73, 40.34 to 135.17, and 66.92 to 290.86 Bq/kg with an average of 76.52, 109.95, and 170.72 Bq/kg, respectively; while in fly ash brick samples, these radionuclides ranged from 42.43 to 71.60, 76.65 to 208.37, and 94.32 to 489.42 Bq/kg with an average of 53.83, 101.93, and 266.48 Bq/kg, respectively. The exhalation rates of 222Rn and 220Rn in all determined samples were in the range of 1.13-20.50 and 15.60-113.00 mBq/m2s, respectively. The calculated results of the radium equivalent activity, external hazard index, internal hazard index, indoor annual effective dose and outdoor annual effective dose indicated that fly ashes and fly ash bricks collected from some brick factories of Baotou would pose excessive radiation risks to inhabitants and that they are not suitable for use in building construction. The natural radioactivity level of fly ash and fly ash brick needs to be constantly monitored considering the radiation safety of the local residents.

Scintigraphy with 99m Tc-Phosphonate and 67Gallium in Patients Suspected of Primary Bone Tumors

1982 ◽  
Vol 21 (04) ◽  
pp. 136-139 ◽  
Author(s):  
C.-J. Edeling
Keyword(s):  
Soft Tissue ◽  
Bone Scintigraphy ◽  
Primary Tumor ◽  
Bone Tumors ◽  
Whole Body ◽  
Skeletal Metastases ◽  
Malignant Bone Tumors ◽  
67Ga Scintigraphy ◽  
Primary Bone Tumors ◽  
Primary Bone

Whole-body scintigraphy with both 99mTc-phosphonate and 67Ga was performed on 92 patients suspected of primary bone tumors. In 46 patients with primary malignant bone tumors, scintigraphy with 99mTc-phosphonate disclosed the primary tumor in 44 cases and skeletal metastases in 11, and 67Ga scintigraphy detected the primary tumor in 43 cases, skeletal metastases in 6 cases and soft-tissue metastases in 8 cases. In 25 patients with secondary malignant bone tumors, bone scintigraphy visualized a single lesion in 10 cases and several lesions in 15 cases, and 67Ga scintigraphy detected the primary tumor in 17 cases, skeletal metastases in 17 cases and soft-tissue metastases in 9 cases. In 21 patients with benign bone disease positive uptake of 99mTc-phosphonate was recognized in 19 cases and uptake of 67Ga in 17 cases. It is concluded that bone scintigraphy should be used in patients suspected of primary bone tumors. If malignancy is suspected, 67Ga scintigraphy should be performed in addition.

The Measurements of Natural Radioactivity, (Radon and Gamma concentrations), around the old fertilizer factory in Basrah/Iraq

2015 ◽  
Vol 7 (1) ◽  
pp. 1324-1335
Author(s):  
Jabbar H. Jebur
Keyword(s):  
Effective Dose ◽  
Radon Concentration ◽  
Gamma Ray ◽  
Annual Effective Dose ◽  
Track Detector ◽  
Exhalation Rate ◽  
Hazard Indices ◽  
Radium Equivalent ◽  
Passive Technique ◽  
Radium Activity

Radon concentration, exhalation rate, annual effective dose, radium activity, thorium, uranium potassium and radium equivalent have been measured in the present investigation for soil in the area around the old fertilizer factory in southern of Basrah Governorate. The measurements based on CR39 track detector for passive method, RAD7 for active method and NaI(Tl) for gamma concentration measurements. Average values for radon concentration in soil were 112.04±10.76 Bq/m3 using passive technique and 104.56±6.05 Bq/m3 using RAD7. From the result of the passive technique, area and mass exhalation rates and the annual effective dose were calculated. Gamma ray spectroscopy for the soil samples were performed and found that the average concentrations of 226Ra, 232Th and 40K were 50.89 Bq/kg, 21.74 Bq/kg and 640.4 Bq/kg respectively. Gamma ray hazard indices were calculated and found they are within the world average.

Radiation exposure of the staff at the therapeutic and diagnostic nuclear medicine department

2008 ◽  
Vol 47 (04) ◽  
pp. 175-177 ◽  
Author(s):  
J. Dolezal
Keyword(s):  
Nuclear Medicine ◽  
Radiation Exposure ◽  
Effective Dose ◽  
Radiation Protection ◽  
Annual Effective Dose ◽  
Protection Measures ◽  
Professional Groups ◽  
Personal Dosimetry ◽  
The Mean ◽  
Administered Activity

SummaryAim: To assess a radiation exposure and the quality of radiation protection concerning a nuclear medicine staff at our department as a six-year retrospective study. Therapeutic radionuclides such as 131I, 153Sm, 186Re, 32P, 90Y and diagnostic ones as a 99mTc, 201Tl, 67Ga, 111In were used. Material, method: The effective dose was evaluated in the period of 2001–2006 for nuclear medicine physicians (n = 5), technologists (n = 9) and radiopharmacists (n = 2). A personnel film dosimeter and thermoluminescent ring dosimeter for measuring (1-month periods) the personal dose equivalent Hp(10) and Hp(0,07) were used by nuclear medicine workers. The wearing of dosimeters was obligatory within the framework of a nationwide service for personal dosimetry. The total administered activity of all radionuclides during these six years at our department was 17,779 GBq (99mTc 14 708 GBq, 131I 2490 GBq, others 581 GBq). The administered activity of 99mTc was similar, but the administered activity of 131I in 2006 increased by 200%, as compared with the year 2001. Results: The mean and one standard deviation (SD) of the personal annual effective dose (mSv) for nuclear medicine physicians was 1.9 ± 0.6, 1.8 ± 0.8, 1.2 ± 0.8, 1.4 ± 0.8, 1.3 ± 0.6, 0.8 ± 0.4 and for nuclear medicine technologists was 1.9 ± 0.8, 1.7 ± 1.4, 1.0 ± 1.0, 1.1 ± 1.2, 0.9 ± 0.4 and 0.7 ± 0.2 in 2001, 2002, 2003, 2004, 2005 and 2006, respectively. The mean (n = 2, estimate of SD makes little sense) of the personal annual effective dose (mSv) for radiopharmacists was 3.2, 1.8, 0.6, 1.3, 0.6 and 0.3. Although the administered activity of 131I increased, the mean personal effective dose per year decreased during the six years. Conclusion: In all three professional groups of nuclear medicine workers a decreasing radiation exposure was found, although the administered activity of 131I increased during this six-year period. Our observations suggest successful radiation protection measures at our department.

scholarly journals Whole Body Low Dose Computed Tomography Using Third-Generation Dual-Source Multidetector With Spectral Shaping: Protocol Optimization and Literature Review

Dose-Response ◽  
2020 ◽  
Vol 18 (4) ◽  
pp. 155932582097313
Author(s):  
Dario Baldi ◽  
Liberatore Tramontano ◽  
Vincenzo Alfano ◽  
Bruna Punzo ◽  
Carlo Cavaliere ◽  
...  
Keyword(s):  
Effective Dose ◽  
Low Dose ◽  
Whole Body ◽  
Dose Length Product ◽  
Osteolytic Lesions ◽  
Subjective Image Quality ◽  
Ct Dose ◽  
Dual Source ◽  
Ct Dose Index ◽  
Low Dose Computed Tomography

For decades, the main imaging tool for multiple myeloma (MM) patient’s management has been the conventional skeleton survey. In 2014 international myeloma working group defined the advantages of the whole-body low dose computed tomography (WBLDCT) as a gold standard, among imaging modalities, for bone disease assessment and subsequently implemented this technique in the MM diagnostic workflow. The aim of this study is to investigate, in a group of 30 patients with a new diagnosis of MM, the radiation dose (CT dose index, dose-length product, effective dose), the subjective image quality score and osseous/extra-osseous findings rate with a modified WBLDCT protocol. Spectral shaping and third-generation dual-source multidetector CT scanner was used for the assessment of osteolytic lesions due to MM, and the dose exposure was compared with the literature findings reported until 2020. Mean radiation dose parameters were reported as follows: CT dose index 0.3 ± 0.1 mGy, Dose-Length Product 52.0 ± 22.5 mGy*cm, effective dose 0.44 ± 0.19 mSv. Subjective image quality was good/excellent in all subjects. 11/30 patients showed osteolytic lesions, with a percentage of extra-osseous findings detected in 9/30 patients. Our data confirmed the advantages of WBLDCT in the diagnosis of patients with MM, reporting an effective dose for our protocol as the lowest among previous literature findings.

scholarly journals Human Biodistribution and Radiation Dosimetry of the P-Glycoprotein Radiotracer [11C]Metoclopramide

2021 ◽  
Author(s):  
Martin Bauer ◽  
Sandra Barna ◽  
Matthias Blaickner ◽  
Konstantin Prosenz ◽  
Karsten Bamminger ◽  
...  
Keyword(s):  
Urinary Bladder ◽  
Healthy Volunteers ◽  
Effective Dose ◽  
Left Kidney ◽  
Whole Body ◽  
Red Bone Marrow ◽  
Body Distribution ◽  
P Glycoprotein ◽  
Pet Tracer ◽  
Male Subjects

Abstract Purpose To assess in healthy volunteers the whole-body distribution and dosimetry of [11C]metoclopramide, a new positron emission tomography (PET) tracer to measure P-glycoprotein activity at the blood-brain barrier. Procedures Ten healthy volunteers (five women, five men) were intravenously injected with 387 ± 49 MBq of [11C]metoclopramide after low dose CT scans and were then imaged by whole-body PET scans from head to upper thigh over approximately 70 min. Ten source organs (brain, thyroid gland, right lung, myocardium, liver, gall bladder, left kidney, red bone marrow, muscle and the contents of the urinary bladder) were manually delineated on whole-body images. Absorbed doses were calculated with QDOSE (ABX-CRO) using the integrated IDAC-Dose 2.1 module. Results The majority of the administered dose of [11C]metoclopramide was taken up into the liver followed by urinary excretion and, to a smaller extent, biliary excretion of radioactivity. The mean effective dose of [11C]metoclopramide was 1.69 ± 0.26 μSv/MBq for female subjects and 1.55 ± 0.07 μSv/MBq for male subjects. The two organs receiving the highest radiation doses were the urinary bladder (10.81 ± 0.23 μGy/MBq and 8.78 ± 0.89 μGy/MBq) and the liver (6.80 ± 0.78 μGy/MBq and 4.91 ± 0.74 μGy/MBq) for female and male subjects, respectively. Conclusions [11C]Metoclopramide showed predominantly renal excretion, and is safe and well tolerated in healthy adults. The effective dose of [11C]metoclopramide was comparable to other 11C-labeled PET tracers.

scholarly journals Radon Activity Concentrations in Natural Hot Spring Water: Dose Assessment and Health Perspective

2021 ◽  
Vol 18 (3) ◽  
pp. 920
Author(s):  
Eka Djatnika Nugraha ◽  
Masahiro Hosoda ◽  
June Mellawati ◽  
Untara Untara ◽  
Ilsa Rosianna ◽  
...  
Keyword(s):  
Public Health ◽  
Effective Dose ◽  
Radiation Protection ◽  
Water Samples ◽  
Hot Springs ◽  
Hot Spring ◽  
Annual Effective Dose ◽  
Spring Water ◽  
Dose Assessment ◽  
West Java

The world community has long used natural hot springs for tourist and medicinal purposes. In Indonesia, the province of West Java, which is naturally surrounded by volcanoes, is the main destination for hot spring tourism. This paper is the first report on radon measurements in tourism natural hot spring water in Indonesia as part of radiation protection for public health. The purpose of this paper is to study the contribution of radon doses from natural hot spring water and thereby facilitate radiation protection for public health. A total of 18 water samples were measured with an electrostatic collection type radon monitor (RAD7, Durridge Co., USA). The concentration of radon in natural hot spring water samples in the West Java region, Indonesia ranges from 0.26 to 31 Bq L−1. An estimate of the annual effective dose in the natural hot spring water area ranges from 0.51 to 0.71 mSv with a mean of 0.60 mSv for workers. Meanwhile, the annual effective dose for the public ranges from 0.10 to 0.14 mSv with an average of 0.12 mSv. This value is within the range of the average committed effective dose from inhalation and terrestrial radiation for the general public, 1.7 mSv annually.

MEASUREMENT OF THE ACTIVITY CONCENTRATIONS OF GAMMA EMITTING RADIONUCLIDES IN TOOTHPASTE SAMPLES AND ASSESSMENT OF THE CORRESPONDING ANNUAL EFFECTIVE DOSES

2021 ◽  
Author(s):  
Anas M Ababneh ◽  
Qutad M Samarah
Keyword(s):  
Effective Dose ◽  
Oral Hygiene ◽  
Annual Effective Dose ◽  
Daily Basis ◽  
Dose Assessment ◽  
Accidental Ingestion ◽  
Activity Concentrations ◽  
Effective Doses

Abstract It is inevitable that we are exposed to radiation daily from various sources and products that we consume on daily basis. The use of toothpaste for oral hygiene is one of the most common daily practices by humans and yet very little data are available regarding its radiation content. In this work, we investigated the concentrations of gamma emitting radionuclides in toothpaste samples consumed in Jordan. 40K and 226Ra were detected in almost one-third of the samples, whereas 228Ra was detected in nearly half of them. The corresponding activity concentrations in the detected samples were in the ranges of 68.7–154.2, 4.6–14.1 and 1.3–10.0 Bq/kg, respectively. Dose assessment of accidental ingestion of toothpaste for children and adults was made, and its contribution to the annual effective dose was found to be very minimal with maximum doses of ~2.9 and 1.3 μSv for children and adults, respectively.

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