MEASUREMENT OF OPERATIONAL DOSIMETRY QUANTITIES FOR NUCLEAR MEDICINE STAFF

2020 ◽  
Vol 190 (2) ◽  
pp. 119-124
Author(s):  
Nahid Dehghan ◽  
Sedigheh Sina
Keyword(s):  
Nuclear Medicine ◽  
Dose Equivalent ◽  
Alara Principle ◽  
Film Badge ◽  
Good Consistency ◽  
Dose Limits ◽  
Staff Protection ◽  
Personal Dosimetry ◽  
Operational Quantities

Abstract According to the ALARA principle, exposure to radiation should be reduced as low as reasonably achievable. This principle is very important in nuclear medicine (NM), and different investigations have been performed by establishing protocols and standards for staff protection. This study aims to measure the operational quantities, personal dose equivalent, Hp (10), Hp (0.07) and Hp (3) for NM staff in Shiraz hospitals, and comparison with dose limits. Two types of dosimeters, TLD-100 and GR-200, were used in this study. In the first step, the calibration of dosimeters was performed using different phantoms. Then, a group of dosimeters was prepared and used for 1 month on the heads, wrists and chests of the staff for measurement of Hp (3), Hp (0.07) and Hp (10), respectively. The obtained values of Hp (10) were compared with the results of their personal dosimetry, film badge. The results of this study show good consistency in the measurements using the two dosimeters.

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.

Proposed Dose Constraints in the Duties of Radiation Workers at the Department of Nuclear Medicine

2019 ◽  
Vol 187 (4) ◽  
pp. 535-539
Author(s):  
Woon-Kwan Chung ◽  
Nam-Hee Yang ◽  
Kyung-Rae Dong ◽  
Jiwon Choi
Keyword(s):  
Nuclear Medicine ◽  
Exposure Dose ◽  
Individual Exposure ◽  
Limit Value ◽  
Positron Emission ◽  
Pet Ct ◽  
Dose Constraint ◽  
Dose Limits ◽  
The Individual ◽  
Dose Constraints

Abstract This study aimed to set a dose constraint for certain duties of radiological technologists in the department of nuclear medicine. From 2013 to 2017, the 5 y radiation exposure data of employees performing PET-CT and γ-CAMERA of eight hospitals in Korea were measured individual exposure doses to estimate the frequency and set a representative dose of 75 and 95% from the low dose in the whole category is presented. The dose constraint was 5.5 mSv for PET-CT, 4.5 mSv for γ-CAMERA and 3.5 mSv for Positron Emission Tomography (PET)-Computed Tomography(CT) and Gamma CAMERA (γ-CAMERA). Therefore, it would be appropriate to set a dose-limit value of ~5 mSv corresponding to 75–80% of the individual exposure dose of radiological technologists in the department of nuclear medicine. The finding of this study may be used as reference data for setting future radiation dose limits.

INFLUENCE OF NEW MASS ENERGY-ABSORPTION COEFFICIENTS FROM ICRU REPORT NO. 90 ON AIR KERMA TO DOSE EQUIVALENT CONVERSION COEFFICIENTS

2018 ◽  
Vol 185 (1) ◽  
pp. 27-33
Author(s):  
Katharina Bairlein ◽  
Oliver Hupe
Keyword(s):  
Energy Absorption ◽  
Radiation Protection ◽  
Cross Sections ◽  
Mass Energy ◽  
Dose Equivalent ◽  
Absorption Coefficients ◽  
X Ray ◽  
Air Kerma ◽  
Conversion Coefficients ◽  
Operational Quantities

Abstract In Report No. 90 of the International Commission on Radiation Units and Measurements (ICRU), new mass energy-absorption coefficients are listed which are based on renormalized Scofield photoeffect cross-sections. The mass energy-absorption coefficients are the basis for the conversion coefficients from air kerma to the operational quantities listed in ISO 4037-3. Although ICRU does not give a recommendation if these new mass energy-absorption coefficients should be applied instead of the values used so far, an examination of the possible consequences for radiation protection quantities is necessary. We calculated the conversion coefficients for the X-ray qualities specified in ISO 4037-1 with the new mass energy-absorption coefficients and with the mass energy-absorption coefficients used so far to determine the deviations. Our calculations show that the change of the conversion coefficients due to the new values from ICRU Report No. 90 is negligible.

scholarly journals ESTIMATION OF HP(3) AMONG STAFF MEMBERS IN TWO NUCLEAR MEDICINE UNITS IN FINLAND

2020 ◽  
Vol 190 (2) ◽  
pp. 176-184
Author(s):  
C Lindholm ◽  
A Pekkarinen ◽  
O Sipilä ◽  
A-L Manninen ◽  
M Lehtinen ◽  
...  
Keyword(s):  
Nuclear Medicine ◽  
Eye Lens ◽  
Dose Measurement ◽  
Individual Dose ◽  
Dose Equivalent ◽  
University Hospitals ◽  
Staff Members

Abstract The eye lens exposure among 16 technicians in two nuclear medicine departments at university hospitals in Finland was investigated by measuring the operational quantity Hp(3) using EYE-D dosemeters. For all workers, the annual mean Hp(3) was estimated to be 1.1 mSv (max. 3.9 mSv). The relation between Hp(3) to routinely monitored personal dose equivalent Hp(10) was clearly correlated. Considering individual dose measurement periods (2–4 weeks), the Hp(3)/Hp(10) ratio was 0.7 (Pearson’s coefficient r = 0.90, p < 0.001, variation of ratio 0.1–2.3). The variation decreased considerably with increasing Hp(10) (σ2 = 0.04 vs. 0.43 for Hp(10) > 0.1 mSv vs. < 0.1 mSv, respectively), i.e. higher Hp(10) predicts Hp(3) more reliably. Moreover, annual Hp(10) data from national dose register during 2009–2018 were used to derive the annual Hp(3) applying the Hp(3)/Hp(10) ratio. The data from Finnish nuclear medicine departments imply that routine measurements of Hp(3) among nuclear medicine technicians are not justified.

UNCERTAINTY EVALUATION IN MEASUREMENT OF THE PERSONAL DOSE EQUIVALENT AT NINE INDIVIDUAL MONITORING SERVICES IN ASIA AND THE PACIFIC REGION

2020 ◽  
Vol 190 (2) ◽  
pp. 217-225
Author(s):  
Chadia Rizk ◽  
Panagiotis Askounis ◽  
H Burçin Okyar ◽  
John Konsoh Sangau ◽  
Samaneh Baradaran ◽  
...  
Keyword(s):  
Uncertainty Evaluation ◽  
Radiological Protection ◽  
International Electrotechnical Commission ◽  
Pacific Region ◽  
Dose Equivalent ◽  
Annual Dose ◽  
Uncertainty In Measurement ◽  
The Pacific ◽  
Dose Limits ◽  
Relevant Dose

Abstract This paper presents the results of the evaluation of the uncertainty in measurement of the personal dose equivalent, Hp(10), at nine individual monitoring services (IMSs) in Asia and the Pacific region. Different types of passive dosemeters were type-tested according to the International Electrotechnical Commission 62387 requirements. The uncertainty in measurement was calculated using the Guide to the Expression of Uncertainty in Measurement approach. Expanded uncertainties ranged between 24 and 86% (average = 38%) for Hp(10) values around 1 mSv and between 14 and 40% (average = 27%) for doses around the annual dose limit, Hp(10) = 20 mSv. The expanded uncertainties were lower than the 1.5 factor in either direction proposed by the International Commission on Radiological Protection for doses near the relevant dose limits. This indicates an acceptable level of uncertainty for all participating IMSs. Uncertainty evaluation will help the IMSs to acknowledge the accuracy of their measurements.

scholarly journals Evaluation of syringe shield effectiveness in handling radiopharmaceuticals

2015 ◽  
Vol 30 (2) ◽  
pp. 158-163 ◽  
Author(s):  
Yong-In Cho ◽  
Chang-Soo Kim ◽  
Jung-Hoon Kim
Keyword(s):  
Nuclear Medicine ◽  
Radiation Source ◽  
Skin Surface ◽  
Shielding Effect ◽  
Shield Effectiveness ◽  
Radiation Shield ◽  
Dose Equivalent ◽  
Dose Evaluation ◽  
Radiation Sources

The purpose of this study was to evaluate the effectiveness of the radiation shield of radionuclide syringes and the personal dose equivalent by performing a simulation of radionuclides used in nuclear medicine diagnosis. In order to evaluate the dose depending on the distance between the radiation source and the ICRU sphere against the thickness of the shielding device, the distance at which a nuclear medicine worker may inadvertently come into contact with radiation from the radiation source was set at 0 cm to 30 cm according to the thickness of the shield, thus fixing the ICRU sphere. For a dose evaluation, Hp(10), Hp(3), and Hp(0.07) measurable in specific depth of the ICRU were evaluated. It was found that a dose measured on skin surface of nuclear medicine workers was relatively higher, that the dose varied in relation to the thickness of the radiation shield, and that the shielding effect decreased for some radiation sources such as 67Ga and 111In. It proved necessary to increase thickness of shielding device to the radiation sources such as 67Ga and 111In. It is also considered that a study of proper shielding thickness will be needed in future.

Principles and control methods

2015 ◽  
Author(s):  
Karen E Goldstone
Keyword(s):  
Radiation Protection ◽  
Control Measures ◽  
Risk Assessments ◽  
Control Methods ◽  
Alara Principle ◽  
Radiation Sources ◽  
Dose Limits ◽  
Dose Constraints ◽  
And Control ◽  
Dose Levels

Justification, optimization, and limitation are the three underlying principles of good radiation protection. This chapter considers how these principles apply in a variety of exposure situations. Risk-based application of the principles results in control methods comprising control over areas, control over people, and control over radiation sources. These are implemented through judgements based on the use of dose limits, dose constraints, and application of the ALARA principle. Potential dose levels and possible control measures appropriate to each situation are reviewed and evaluated in risk assessments prior to work being undertaken.

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