Radiation doses deriving from patients treated with 166Ho-ferric hydroxide

2003 ◽  
Vol 42 (06) ◽  
pp. 251-254
Author(s):  
C. Pirich ◽  
P. John ◽  
S. Ofluoglu ◽  
H. Sinzinger ◽  
E. Havlik ◽  
...  
Keyword(s):  
Radiation Exposure ◽  
Radiation Protection ◽  
Ferric Hydroxide ◽  
Medical Personnel ◽  
Whole Body ◽  
Radiation Doses ◽  
Annual Dose ◽  
Tracer Injection ◽  
Dose Rates ◽  
Protection Devices

Summary Aim: To estimate radiation doses deriving from patients treated with 166Ho ferric hydroxide. Methods: For radiation synoviorthesis about 900 ± 100 MBq 166Ho ferric hydroxide was injected into the knee joint of 16 patients. To estimate the radiation exposure of persons in the neighbourhood of the patients measurements of the dose rates were performed at 0.5 m, 1 m and 2 m distance of the treated joint 10 min after tracer injection. Measurements were carried out with and without radiation protection devices of the syringe. Results: The initial values of the dose rate were 11.9 μSv/h at 0.5 m, 3.5 μSv/h at 1 m and 1 μSv/h at 2 m distance, respectively. The whole body doses were 2.9 μSv for the physician and 4.6 μSv for the technologist. The finger doses for the technologist and the physician were ranging from 65 to 111 μSv. After discharge at home other persons might receive 118 μSv. Conclusion: Our results, under very strict assumptions, clearly demonstrate that the calculated radiation exposure to medical and non medical personnel is well below the maximum annual dose limit. The use of any additional radiation protection device as syringe shielding does not significantly lower radiation exposure.

Radioiodine treatment of feline hyperthyroidism in Germany

2002 ◽  
Vol 41 (06) ◽  
pp. 245-251 ◽  
Author(s):  
M. Knietsch ◽  
T. Spillmann ◽  
E.-G. Grünbaum ◽  
R. Bauer ◽  
M. Puille
Keyword(s):  
Radiation Exposure ◽  
Radiation Protection ◽  
Thyroid Function ◽  
Radioiodine Therapy ◽  
Whole Body ◽  
Radioiodine Treatment ◽  
Normal Thyroid ◽  
Normal Thyroid Function ◽  
Body Activity ◽  
Thyroid Uptake

SummaryAim: Establishment of radioiodine treatment of feline hyperthyroidism in veterinary routine in accordance with German radiation protection regulations. Patients and methods: 35 cats with proven hyperthyroidism were treated with 131I in a special ward. Thyroid uptake and effective halflife were determined using gammacamera dosimetry. Patients were released when measured whole body activity was below the limit defined in the German “Strahlenschutzverordnung”. Results: 17/20 cats treated with 150 MBq radioiodine and 15/15 cats treated with 250 MBq had normal thyroid function after therapy, normal values for FT3 and FT4 were reached after two and normal TSH levels after three weeks. In 14 cats normal thyroid function was confirmed by controls 3-6 months later. Thyroidal iodine uptake was 24 ± 10%, effective halflife 2.5 ± 0.7 days. Whole body activity <1 MBq was reached 13 ± 4 days after application of 131I. Radiation exposure of cat owners was estimated as 1.97 Sv/MBq for adults. Conclusion: Radioiodine therapy of feline hyper-thyroidism is highly effective and safe. It can easily be performed in accordance with German radiation protection regulations, although this requires hospitalisation for approximately two weeks. Practical considerations on radiation exposure of cat owners do not justify this long interval. Regulations for the veterinary use of radioactive substances similar to existing regulations for medical use in humans are higly desirable.

scholarly journals Intraoperative 2D C-arm and 3D O-arm in children: a comparative phantom study

2018 ◽  
Vol 12 (5) ◽  
pp. 550-557 ◽  
Author(s):  
M. Prod’homme ◽  
M. Sans-Merce ◽  
N. Pitteloud ◽  
J. Damet ◽  
P. Lascombes
Keyword(s):  
Radiation Exposure ◽  
Scattered Radiation ◽  
Intraoperative Imaging ◽  
Radiation Doses ◽  
Organ Doses ◽  
Thermoluminescent Dosimeters ◽  
Dose Rates ◽  
Absorbed Doses ◽  
Entrance Dose ◽  
Student’S T

Purpose Exposure to ionizing radiation is a concern for children during intraoperative imaging. We aimed to assess the radiation exposure to the paediatric patient with 2D and 3D imaging. Methods To evaluate the radiation exposure, patient absorbed doses to the organs were measured in an anthropomorphic phantom representing a five-year-old child, using thermoluminescent dosimeters. For comparative purposes, organ doses were measured using a C-arm for one minute of fluoroscopy and one acquisition with an O-arm. The cone-beam was centred on the pelvis. Direct and scattered irradiations were measured and compared (Student’s t-test). Skin entrance dose rates were also evaluated. Results All radiation doses were expressed in µGy. Direct radiation doses of pelvic organs were between 631.22 and 1691.87 for the O-arm and between 214.08 and 737.51 for the C-arm, and were not significant (p = 0.07). Close scattered radiation on abdominal organs were between 25.11 and 114.85 for the O-arm and between 8.03 and 55.34 for the C-arm, and were not significant (p = 0.07). Far scattered radiation doses on thorax, neck and head varied from 0.86 to 6.42 for the O-arm and from 0.04 to 3.08 for the C-arm, and were significant (p = 0.02). The dose rate at the skin entrance was 328.58 µGy.s−1 for the O-arm and 1.90 with the C-arm. Conclusion During imaging of the pelvis, absorbed doses for a 3D O-arm acquisition were higher than with one minute fluoroscopy with the C-arm. Further clinical studies comparing effective doses are needed to assess ionizing risks of the intraoperative imaging systems in children.

scholarly journals Radiation protection effect of mobile shield barrier for the medical personnel during endoscopic retrograde cholangiopancreatography: a quasi-experimental prospective study

BMJ Open ◽  
2019 ◽  
Vol 9 (3) ◽  
pp. e027729 ◽  
Author(s):  
Kwang Hyun Chung ◽  
Young Sook Park ◽  
Sang Bong Ahn ◽  
Byoung Kwan Son
Keyword(s):  
Radiation Dose ◽  
Prospective Study ◽  
Radiation Protection ◽  
Endoscopic Retrograde Cholangiopancreatography ◽  
Medical Personnel ◽  
Secondary Outcome ◽  
Radiation Doses ◽  
Endoscopic Retrograde ◽  
Quasi Experimental ◽  
The Mean

ObjectiveTo investigate the effectiveness of radiation protection offered by a newly designed mobile shield barrier for medical personnel during endoscopic retrograde cholangiopancreatography (ERCP).DesignQuasi-experimental prospective study.SettingERCP procedures conducted between October 2016 and June 2017 at a single secondary referral hospital that performs approximately 250 therapeutic ERCP procedures annually.InterventionsThe mobile shield barrier was a custom-made 2 mm Pb shielding plate (width: 120 cm, height: 190 cm) with a 0.5 mm Pb window (width: 115 cm, height: 60 cm) on its upper part was used. Four wheels were attached to the bottom to allow easy moving.Primary and secondary outcome measuresThe radiation doses were measured during ERCP using personal thermoluminescence dosimetry (TLD) badges on both sides of the mobile shield barrier (patient’s side: TLD1 and medical staff’s side: TLD2). The radiation doses were also measured on the outer surface of the thyroid shield of the endoscopist (TLD3), and on the chest area inside the protective apron of the endoscopist (TLD4) and the main assistant (TLD5). The TLD was changed and reported once every 3 months. The radiation dose measured by TLD badges were compared.ResultsDuring the study period, a total of 128 ERCP procedures were performed. The mean fluoroscopy time per procedure was 244.9±257.0 s and the mean number of digital radiographs per procedure was 3.7±1.0. TLD1 (outside the barrier) had a mean radiation dose of 26.85±3.47 mSv and all the other TLDs (inside the barrier) had less than 1 mSv (p<0.001). In the post hoc analysis, the difference between TLD1 and others showed a statistical significance; however, there were no significant differences between the TLDs inside the barrier.ConclusionOur mobile shield barrier was useful to reduce the radiation exposure of medical personnel during ERCP.

Investigation concerning the Radiation Exposure of the Medical Personnel during F-l8-FDG-PET Studies

2000 ◽  
Vol 39 (03) ◽  
pp. 77-81 ◽  
Author(s):  
E. Will ◽  
B. Beuthien-Baumann ◽  
H. Linemann
Keyword(s):  
Radiation Exposure ◽  
Fdg Pet ◽  
Medical Personnel ◽  
Radiation Shielding ◽  
Annual Dose ◽  
Radiation Level ◽  
Left Hand ◽  
Thermoluminescent Dosimeters ◽  
Reduce Radiation Exposure ◽  
The Mean

Summary Aim: The aim of the investigation was the identification of those working steps with the highest radiation exposure for the medical personnel during F-l8-FDG-PET studies and to evaluate the effectiveness of radiation protection devices and instructions developed in our PET-center. Methods: The personal dose and hand dose were measured for each working procedure during F-l8-FDG-PET studies using electronic personal dosimeters and thermoluminescent dosimeters respectively. Additionally, measurements of the radiation level near the patient were taken. Results: The mean personal dose resulting from syringe preparation was 1 μSv/syringe, from injection 3 μSv/patient, from blood sampling during quantitative studies 6 μSv/study, and from positioning and handling of the patient 6 μSv/study. The mean hand dose per syringe preparation was 710 μSv for each hand. The mean hand dose during injection was 13 μSv for the right hand and 27 μSv for the left hand. All above mentioned values were measured applying the routine radiation shielding in use in our PET center. Conclusion: With the developed radiation shielding and means to reduce radiation exposure applied the allowed annual dose for medical personnel are not exceeded. One exception is the hand dose resulting from syringe preparation. An automatic or remote filling device should be used at this working step.

EVALUATION OF RADIATION DOSE IN DIFFERENT POSITIONS AROUND THE PATIENT TABLE DURING INTERVENTIONAL CARDIOLOGY PROJECTIONS

2019 ◽  
Vol 188 (2) ◽  
pp. 199-204
Author(s):  
Y Lahfi ◽  
A Ismail
Keyword(s):  
Radiation Dose ◽  
Radiation Exposure ◽  
Dose Rate ◽  
Radiation Protection ◽  
Interventional Cardiology ◽  
X Ray ◽  
Dose Rates ◽  
Patient Table ◽  
The Right

Abstract The aim of the present study was to evaluate the radiation exposure around the patient table as relative to the cardiologist position dose value. The dose rates at eight points presuming staff positions were measured for PA, LAO 30° and RAO 30° radiographic projections, and then normalized to the cardiologist’s position dose-rate value. The results show that in PA and RAO 30° projections, the normalized dose rate was higher by 9–22% at the right side of the table at a distance of 50 cm, while it was higher up to 31% at the left side for the same measured points in the LAO 30°. The differences of normalized dose rates for the both table sides were lower and decreased at farther positions. The obtained results correspond to the recommendations of staff radiation protection in Cath-labs with regards to X-ray tube and detector positions.

Radiation exposure in the environment of patients after application of radiopharmaceuticals

2009 ◽  
Vol 48 (01) ◽  
pp. 17-25 ◽  
Author(s):  
F. Boldt ◽  
C. Kobe ◽  
J. Hammes ◽  
W. Eschner ◽  
H. Schicha ◽  
...  
Keyword(s):  
Radiation Exposure ◽  
Radiation Protection ◽  
High Energy ◽  
Radioactive Source ◽  
Detailed Knowledge ◽  
Dose Rates ◽  
Diagnostic Nuclear Medicine ◽  
Photon Dose ◽  
High Maximum ◽  
Radiation Measurements

Summary Aim: After therapeutical application of radionuclides the patient has to be regarded as a radioactive source. The radiation exposure differs from diagnostic nuclear medicine due to the amount of radioactivity and due to β-radiation. Measurements of photon dose rates were carried out and estimates of β-radiation outside the patient using Monte-Carlo methods. Calculations of maximum β-ranges in tissue were also performed. Detailed knowledge of the radiation exposure close to the patient is of major importance with respect to radiation protection of the staff. Method: Photon dose rates for 32 patients were determined after treatment with [131I]NaI and [131I]meta-iodobenzylguanidin, [32P]Na2HPO4, [90Y]Zevalin and [153Sm]EDTMP. Readings were taken immediately after application at eight distances. Results: For therapies with 131I photon dose rates amount to 2 mSv·h-1·GBq-1 close to the patient. Taking the typical activities of 3.7 GBq for thyroid carcinoma and up to 11 GBq for mIBG therapies into account this leads to a considerable radiation exposure of approximately 7.5 mSv/h and 20 mSv/h, respectively. At a distance of 2 m the dose rates fall to 1/100 compared to the vicinity. For 153Sm the maximum of 100 μSv·h-1·GBq-1 is significantly lower compared to therapies using radioiodine. After application of 32P or 90Y all photon dose rates are lower (>10 μSv·h-1·GBq-1) but in both cases high energy β-particles associated with high maximum ranges exceeding 1 cm in tissue have to be considered. Conclusion: The remarkable difference of the dose rates in the vicinity of the radioactive patient compared to readings at 2 m distance underlines the major importance of the distance for radiation protection. After application of nuclides emitting high energy β-particles their contribution outside the patient should be considered. For typical procedures in the patient's vicinty the radiation exposure of the personnel remains below the annual limit of 20 mSv.

scholarly journals Annual Radiation Exposure to Workers in a Tertiary Care Hospital in Kashmir : A 10-Year Analysis and Comparison with National Levels of exposure

JMS SKIMS ◽  
2009 ◽  
Vol 12 (2) ◽  
pp. 41-45
Author(s):  
Tanveer A Rather ◽  
Showkat H Khan ◽  
Mohib Ul Haq ◽  
Riyaz A Rangrez ◽  
Ajaz Mustafa
Keyword(s):  
Radiation Exposure ◽  
Tertiary Care Hospital ◽  
Tertiary Care ◽  
Whole Body ◽  
Care Hospital ◽  
Medical Sciences ◽  
Annual Dose ◽  
Medicine Department ◽  
Nuclear Medicine Department ◽  
Radiation Workers

Objective: To assess the radiation exposure amongst radiation workers in Sher-i-Kashmir Institute of Medical Sciences (SKIMS), Srinagar, a tertiary care 620 bedded superspeciality hospital was carried out. Material and Methods: A 10-year retrospective analysis of the whole body radiation exposure to the radiation workers of SKIMS Srinagar, Two blocks of five years each from 1995 to 1999 & 2002 to 2007 were studied and compared with the national pool of radiation workers for the same period. The average annual dose of radiation workers working in different radiation departments of SKIMS was compared with the workers of the similar department of the national pool. Results & Conclusion: It was observed that in the block of 5 years from 1995 to 1999 the average whole body dose to the radiation works at SKIMS during the latter half showed a rising trend for three years as compared to the national pool. However in the block 2002 to 2005 the average annual dose was mostly similar except for a higher dose to SKIMS workers in 2005. It was observed that the average annual dose received by the workers of Nuclear Medicine department of SKIMS was usually high more so in the five year block of 2000 to 2005.The workers of Radiodiagnosis at SKIMS also received a higher annual dose in 7 of the 10 years of study. J Med Sci 2009;12(2):41-45

Коэффициент эффективности (DDREF) дозы и мощноcти доз: ненужные, спорные и противоречивые вопросы

2017 ◽  
Vol 62 (2) ◽  
pp. 13-27
Author(s):  
Julio Abel ◽  
Julio Abel
Keyword(s):  
Radiation Exposure ◽  
Dose Rate ◽  
Radiation Protection ◽  
Radiation Effects ◽  
Radiation Risk ◽  
Mathematical Formulation ◽  
Indirect Evidence ◽  
Dose Rates ◽  
Radiation Risks ◽  
Risk Estimates

Purpose: The aim of the paper is to review the genesis and evolution of the concept termed dose and dose rate effectiveness factor or DDREF, to expose critiques on the concept and to suggest some curse of action on its use. Material and methods: Mainly using the UNSCEAR reporting and ICRP recommendations as the main reference material, the paper describes the evolution (since the 70’s) of the conundrum of inferring radiation risk at low dose and dose-rate. People are usually exposed to radiation at much lower doses and dose rates than those for which quantitative evaluations of incidence of radiation effects are available – a situation that tempted experts to search for a factor relating the epidemiological attribution of effects at high doses and dose-rates with the subjective inference of risk at low doses and dose-rates. The formal introduction and mathematical formulation of the concept by UNSCEAR and ICRP (in the 90’s), is recalled. It is then underlined that the latest UNSCEAR radiation risk estimates did not use a DDREF concept, making it de facto unneeded for purposes of radiation risk attribution. The paper also summarizes the continuous use of the concept for radiation protection purposes and related concerns as well as some current public misunderstandings and apprehension on the DDREF (particularly the aftermath of the Fukushima Dai’ichi NPP accident). It finally discusses epistemological weaknesses of the concept itself. Results: It seems that the DDREF has become superseded by scientific developments and its use has turned out to be unneeded for the purposes of radiation risk estimates. The concept also appears to be arguable for radiation protection purposes, visibly controversial and epistemologically questionable Conclusions: It is suggested that: (i) the use of the DDREF can be definitely abandoned for radiation risk estimates; (ii) while recognizing that radiation protection has different purposes than radiation risk estimation, the discontinuation of using a DDREF for radiation protection might also be considered; (iii) for radiation exposure situations for which there are available epidemiological information that can be scientifically tested (namely which is confirmable and verifiable and therefore falsifiable), radiation risks should continue to be attributed in terms of frequentistic probabilities; and, (iv) for radiation exposure situations for which direct scientific evidence of effects is unavailable or unfeasible to obtain, radiation risks may need to be inferred on the basis of indirect evidence, scientific reasoning and professional judgment aimed at estimating their plausibility in terms of subjective probabilities.

Radiation exposure around patients after administration of 123I-MIBG

2002 ◽  
Vol 41 (05) ◽  
pp. 221-223
Author(s):  
S. Ofluoglu ◽  
J. Preitfellner ◽  
B. J. Fueger ◽  
T. Traub ◽  
C. Novotny ◽  
...  
Keyword(s):  
Radiation Exposure ◽  
Dose Rate ◽  
Half Life ◽  
Maximum Dose ◽  
Radiation Detectors ◽  
Mibg Scintigraphy ◽  
Dose Limit ◽  
Annual Dose ◽  
Dose Rates ◽  
M 12

SummaryAim: Estimation of the radiation exposure to neighbouring patients, personnel and relatives deriving from patients undergoing 123I-MIBG scintigraphy. Methods: For scintigraphic studies, 16 patients with suspected pheocromocytoma were injected with 340 ± 30 MBq 123I-MIBG. Dose rates were measured at a distance of 0.5 m, 1 m, and 2 m after 10 min, 3 h, 21 h, 45 h, and 68 h using three calibrated portable radiation detectors. The measured values were background corrected. Results: Ten minutes after injection the dose rate was 10.5 µS/h at a distance of 0.5 m, 3.78 µS/h at 1 m, and 0.95 µS/h at 2 m. The effective half-life was estimated to 8.68 ± 0.15 h. The maximum dose in a distance of 1 m for neighbouring patients was 46 µS/h, for personnel in a ward 27 µS/h, and to relatives in a distance of 2 m 12 µS/h. Conclusion: This study demonstrates that the calculated exposure to people around patients after 123I-MIBG injection is well below the maximum permissible annual dose limit of 1 mSv for not professionally exposed persons.

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