Colour on-line figures None Colour print figures None

Size: px
Start display at page:

Download "Colour on-line figures None Colour print figures None"

Transcription

1 Journal: Article id: Raddos ncs128 Colour on-line figures None Colour print figures None

2 Radiation Protection Dosimetry (2012), pp. 1 9 doi: /rpd/ncs TEDE PER CUMULATED ACTIVITY FOR FAMILY MEMBERS EXPOSED TO ADULT PATIENTS TREATED WITH 131 I Eun Young Han 1, *, Choonsik Lee 2 and Wesley E. Bolch 3 1 Department of Radiation Oncology, University of Arkansas Medical Sciences, 4301 West Markham Street #771, Little Rock, AR 72205, USA 2 Division of Cancer Epidemiology and Genetics, National Cancer Institute, National Institute of Health, Bethesda, MD 20852, USA 3 J. Crayton Pruitt Family Department of Biomedical Engineering, University of Florida, Gainesville, FL 32611, USA *Corresponding author: eyhan@uams.edu Received March , revised June , accepted June In 1997, the United States Nuclear Regulatory Commission amended its criteria under which patients administered radioactive materials could be released from the hospital. The revised criteria ensures that the total effective dose equivalent (TEDE) to any individual exposed to the released patient will not likely exceed 5 msv. Licensees are recommended to use one of the three options to release the patient in accordance with these regulatory requirements: administered activity, measured dose rate, or patient-specific dose calculation. The NRC s suggested calculation method is based on the assumption that the patient (source) and a family member (target) are each considered to be points in space. This point source/target assumption has been shown to be conservative in comparison to more realistic guidelines. In this present study, the effective doses to family members were calculated using a series of revised Oak Ridge National Laboratory stylised phantoms coupled with a Monte Carlo radiation transport code. A set of TEDE per cumulated activity values were calculated for three different distributions of 131 I (thyroid, abdomen and whole body), various separation distances and two exposure scenarios (face-to-face standing and side-by-side lying). The results indicate that an overestimation of TEDE per cumulated activity based on the point source/target method was >2-fold. The values for paediatric phantoms showed a strong age-dependency, which showed that dosimetry for children should be separately considered instead of using adult phantoms as a substitute. On the basis of the results of this study, a licensee may use less conservative patient-specific release criteria and provide the patient and the family members with more practical dose avoidance guidelines. INTRODUCTION In 1997, the United States Nuclear Regulatory Commission (USNRC) amended its regulations concerning the criteria for the release of patients who have been administered radioactive materials in 10CFR (1). The previous release criteria were based on an administered activity,1110 MBq or a dose rate,0.05 msv h 1 at 1 m (1). The revised criteria now allow licensees to release the patient if the estimated total effective dose equivalent (TEDE) to any other individual from exposure to the released patient is not likely to exceed 5 msv. Licensees should use one of three different options to demonstrate compliance with the regulatory requirements: administered activity, measured dose rate, and patient-specific dose calculations. NUREG-1556, Vol. 9. contains the tables of activities and dose rates not likely to cause doses exceeding 5 msv and describes the methods for calculating doses to other individuals (2). The USNRC adopted the equation of the integrated exposure over infinite time specified in NCRP Report No. 37 (3) as follows: D ¼ 34:6 GQ ot p OF r 2 ð1þ where D is the total dose from exposure to gamma radiation, 34.6 is the conversion factor of 24 h d 1 multiplied by the total integration of decay (1.44), G is the exposure rate constant for a point source in unit of C kg 21 cm 2 MBq 21 h 21, Q o is the administered activity in MBq, 34.6 Q o T p is equal to the cumulated activity ~ A in MBq h, T p is the physical half-life of the radionuclide in days, r is a distance of the point source from the point of interest in meters and OF is the occupancy factor, which represents the fraction of the total time an individual spends at a distance of 1 m from the patient. When one rearranges Equation (1) after replacing D with 5 msv, the maximum administered activity (MBq) (Equation (2)) and the maximum dose rate at 1 m (msv h 1 ) (Equation (3)) can be derived as follows: 5 msv r2 Q o ¼ 34:6GT p OF ð2þ # The Author Published by Oxford University Press. All rights reserved. For Permissions, please journals.permissions@oup.com

3 and GQ o r 2 ¼ 5 msv ð3þ 34:6T p OF As of the third option for the patient-specific dose calculation, licensees can consider a retained activity in the patient, an occupancy factor of less than 0.25 at 1 m, an effective half-life and potential shielding by the patient. As described, all three options provided in NUREG-1556, Vol. 9, use the exposure rate constant G, defined as an exposure rate at a point 1 cm away from a point source with the activity of 1 g of radium (37 MBq ¼ 1 mci). That means that it is assumed that the patient (source) and an exposed individual (target) are each considered to be a point in space. This point source/target assumption ignores attenuation and scattering within the patient and within an exposed individual. It is impossible to take into account different body sizes of exposed individuals depending on ages and realistic source activity distributions inside the patient, which might not be uniformly distributed. These simplifications of the more realistic clinical situations may cause overly conservative estimates of family member doses. To address this issue, Siegel et al. (4) suggested a line-source model to determine doses to an individual exposed to a radioactive patient with an extended activity distribution. They found that the point source method is not suitable up to a certain distance between the patient and an exposed individual depending on the length of the line source. Sparks et al. (5) simulated two simplified mathematical phantoms by assuming the entire body to be a soft tissue using the Monte Carlo (MC) transport code MCNP4A, with the patient and an exposed individual facing each other and 1 m apart. In their work, the point source method was found to overestimate the dose equivalent per cumulated activity by a factor of 2.4. Using two female voxel phantoms in two different distances and orientations, de Carvalho et al. (6) calculated the organ and effective doses for a bystander exposed to the radioactive patient. Recently, they also reported the results of the organ and effective dose calculations using point, line and volume sources which highlighted the over-conservative results caused by the point source method (7). In this study, instead of using exposure rate constant, dose calculation was implemented on the basis of tissue-weighted individual organ doses of the agedependent computational phantom series as target phantoms (hereafter referred to as family members) through the MC transport method. The purpose of this study was to calculate (1) the maximum releasable administered activity in accordance with the E. Y. HAN ET AL. Page 2 of 9 regulatory limit of a 5 msv TEDE, and (2) TEDE per cumulated activity (msv MBq 21 h 21 ), using the MC radiation transport technique coupled with a series of paediatric and adult phantoms in various exposure scenarios. The calculations were undertaken only for 131 I, which is one of most commonly used radioisotopes in the medical use of radioactive materials (8). MATERIALS AND METHODS Revised Oak Ridge National Laboratory phantom series In this study, we employed a revised series of stylised computational phantoms (9) representing the ICRP reference 1, 5, 10 and 15-y-old and adult as previously published by the authors. Several revisions were incorporated into the original Oak Ridge National Laboratory (ORNL) stylised phantoms (10) : (1) insertion of newly published models of the head, brain, kidneys and rectosigmoid colon; (2) explicit delineations of respiratory and extra-pulmonary airways, salivary glands and mucosa layers of urinary bladder and alimentary tract; (3) reference values of elemental tissue compositions and mass densities from ICRP Publication 89 and (4) explicit treatment of left and right tissues within organ pairs. The revised ORNL adult and 15-y hermaphrodite phantoms were used to represent an adult male and a female, respectively, since the 15-y-old phantom was considered to be representative of an adult female (9). Calculations of TEDE per cumulated activity In 2009, the internal dosimetry of the Medical Internal Radiation Dose Committee of the Society of Nuclear Medicine published (11) a revised scheme for the assessment of the absorbed dose to a patient in the therapeutic nuclear medicine as follows. Dðr T Þ¼ ~ A s Sðr T r S Þ ð4þ where A ~ s is a total cumulated activity in the source organ of the patient and S(r T r S )isthes values defined as the mean absorbed dose per cumulated activity from the source organ, r S, to the target organ, r T, in the patient in mgy MBq h 1. Equation (4) is rearranged by replacing r T with an organ of the family member, r FM,T,andr S with a 131 I localisation area in the patient, r PT, to provide the effective dose. Dðr FM Þ¼ A ~ PT X w T Sðr FM; T r PT Þ ð5þ T where Sðr FM; T r PT Þ is the mean absorbed dose per cumulated activity for a specific organ T in a family

4 member exposed to the patient mgy MBq 21 h 21, which is equivalent to the S value in Equation (4). TEDE (msv) and the maximum releasable administered activity (Q o, MBq) can be derived from Equation (5) as Equations (7) and (8), respectively. TEDE ¼ 34:6Q o T P OF X T ¼ 34:6Q o T P OF X T w T Sðr FM; T r PT Þ ð6þ X E i n i fðr FM; T w T i m T 5 msv Q o ¼ 34:6T P OF P P E i n i fðr FM; T w T T i m T r PT Þ i r PT Þ i ð7þ ð8þ where w T is the tissue-weighting factor of International Commission on Radiological Protection (ICRP) Publication 60 (12) for an organ T, E i is the emitted photon energy from the radionuclide 131 I for the ith decay, n i is the radiation yield in ith decay, m T is the target organ mass (kg) and fðr FM; T r PT Þ is the absorbed fraction, which is defined as the fraction of radiation energy E i emitted within the source region of the patient, r PT, that is absorbed in an organ r FM,T in the target phantom. TEDE CALCULATION BY MONTE CARLO MC transport method A general purpose MC transport code, MCNP5 (13), was utilised in the calculations of this study to take into account the realistic source/target geometries and behaviours of radiation particles such as attenuation and scattering. The revised ORNL phantom series were incorporated into the MCNP5 code and elemental tissue compositions and mass densities were also implemented into the code. It is assumed that the radioactive source was uniformly distributed within each source region. Surface source writing file (also called as a phase space file) provided by MCNP5 was used to reduce calculation burdens that could be caused by employing two phantoms at the same time within the same transport medium. In this method, all particle tracks from a source phantom were recorded in the surface source file if an emitted photon crosses the predefined surface between two phantoms. In subsequent calculations, the particle information recorded in the surface source file would be used to irradiate various target phantoms without starting photons again from the source phantom. Monoenergetic photons with the energy ranging from 10 kev to 4 MeV were transported to calculate the absorbed fractions. A total of million photon histories were used to maintain relative errors Figure 1. Three-dimensional lateral views of two phantoms facing each other at various distances ranging from 0.1 to 2 m. Adult male patient phantom is facing 1, 5, 10 and 15-y-old phantoms. Skin and muscle tissues are removed to better visualise the internal organs and skeleton. Page 3 of 9 340

5 within the major organs in a target phantom at,5 %. Since dose deposition in a target phantom due to electron transport is small, mode P was selected. Additionally, the F4 tally was used to score the photon fluences to calculate the absorbed fraction in the red bone marrow and bone surface by applying the fluence-to-dose response function generated by Cristy and Eckerman (10). After a final set of energydependent absorbed fractions of a target phantom for each scenario (see section Scenarios of exposure ) was compiled from the MC calculation, TEDE (msv) per cumulated activity and the maximum releasable administered activity (MBq) were calculated from Equations (7) to (8), respectively and compared with the values by the point source method. A physical half-life (T p )of8.04dandanofof0.25wereused for all calculations. E. Y. HAN ET AL. Scenarios of exposure Three different 131 I source regions (thyroid, abdomen and whole body) in the adult phantom were considered since these 131 I activity localisations have been most likely observed in the patients after radioiodine therapies for hyperthyroidism, radioimmunotherapy, or differentiated thyroid cancer (8, 14, 15). The abdominal source region was defined as a volume covering the lower half of the torso of the adult male phantom. Only the adult male phantom was considered as a source phantom and different target phantoms including 1-, 5-, 10-, 15-y-old, and adult male phantoms were taken into account. Two exposure orientations were simulated: (1) an adult male patient is facing a family member at five different distances (0.1, 0.5, 0.75, 1 and 2 m) (Figures 1 and Figure 2. Three-dimensional depiction of the adult patient phantom (left) with 131 I localised in the abdominal region facing the other adult target phantom (right) at a 1 m distance. A total of 1000 initial photon tracks are visualised by using the Sabrina software and MCNP5. Skin and muscle tissues are removed to better view the internal organs and skeleton. Page 4 of 9 455

6 ) and (2) an adult male patient is lying with an adult female side by side at a distance of 0.3 m (Figure 3). RESULTS AND DISCUSSION Maximum releasable administered activity Table 1 presents the maximum releasable administered activity (MBq) at or below which the adult male patient may be released in the exposure scenario where the patient and a family member are facing each other at different distances when 131 Iis localised in thyroid, abdomen and whole body of the patient. Equation (8) was used to calculate the TEDE CALCULATION BY MONTE CARLO maximum releasable administered activity in accordance with the regulatory limit of 5 msv TEDE. A physical half-life of 8.04 d and an occupancy factor of 0.25 were assumed for these calculations. The maximum releasable activity increases as a distance increases except in the case of the thyroid source. The maximum releasable activities based on the point source/target method (Equation (2)) are lower by a factor of 2.3 on average than the values obtained in this study (Equation (8)). Realistically, licensees can release the adult male patient who has been administered even greater activity by a factor of 2.3 on average when the patient will be facing other family members at a 1 m distance. This finding is consistent with the results of Sparks et al. (5) and de Carvalho et al. (7) Figure 3. Three-dimensional frontal view of adult male patient phantom (left) with an adult female target phantom surrogated by a 15-y phantom side by side at a 0.3 m distance. Skin and muscle tissues are removed to better view the internal organs and skeleton. Page 5 of 9 570

7 E. Y. HAN ET AL. Table 1. Maximum releasable administered activity (MBq) when 131 I is localised within thyroid (THY), abdominal region (ABD) and whole body (WB) in the adult male patient phantom facing the family members with different ages (1, 5, 10, 15-y and adult) at different distances Distance (m) Point method Target phantoms 1 y 5 y 10 y 15 y Adult THY ABD WB THY ABD WB THY ABD WB THY ABD WB THY ABD WB The values (MBq) based on the point source/target method at corresponding distances are also included for realistic comparison Figure 4. TEDE per cumulated activity (msv MBq 21 h 21 ) as a function of the distance of an adult male patient from his family members with different ages facing the patient with 131 I localised in the thyroid Since the actual values of the maximum releasable activity will vary depending on different parameters such as OF, it is desirable for the readers to compare the two methods. TEDE per cumulated activity for patient-specific dose calculation Figures 4 6 show TEDE per cumulated activity (msv MBq 21 h 21 ) to paediatric and adult family members a a function of distance when 131 I is concentrated on thyroid, abdomen and whole body, respectively, in the adult male patient. The NRC default value based on the point source/target method at a 1 m distance is also shown for comparison. In Figure 4, TEDE per cumulated activity decreases rapidly with increasing distances and converges to a single value at 2 m. When a target phantom is a 1- or 5-y-old child, the values are small regardless of distance, which means that a child under the age of 5 y is barely affected by an adult male with the thyroid localisation while they stand on the ground. Figure 5 for the abdomen source region shows that the values decrease rapidly with increasing distances and Page 6 of 9

8 TEDE CALCULATION BY MONTE CARLO Figure 5. TEDE per cumulated activity (msv MBq 21 h 21 ) as a function of distance of an adult male patient from his family members with different ages facing the patient with 131 I localised in the abdomen Figure 6. TEDE per cumulated activity (msv MBq 21 h 21 ) as a function of distance of an adult male patient from his family members with different ages facing the patient with 131 I distributed over whole body converge to an asymptotic value at 0.75 m except in the case of a 1-y-old phantom. TEDE per cumulated activity of a 10-y-old phantom is larger than any other age phantoms, since the height of the phantom is comparable with the level of the abdomen region in the adult patient. General Page 7 of 9

9 E. Y. HAN ET AL. Table 2. TEDE per cumulated activity (msv MBq 21 h 21 ) from the simulation of an adult male patient lying with an adult female at a distance of 0.3 m. Distance (m) Point method Adult male to adult female THY ABD WB I is distributed in the adult male phantoms at three different regions: thyroid (THY), abdominal region (ABD) and whole body (WB). The value based on the point source/target method at 0.3 m is included for realistic comparison behaviour of the TEDE per cumulated activity for the whole body source shown in Figure 6 is very similar to that of the abdomen source region as shown in Figure 5. The values for 10- and 15-y-old phantoms are very close to those for the adult target phantom. For the three types of source distributions, the MC-based values at a distance of 1 m are lower by a factor of 2.3 on average than the NRC value that would have been selected regardless of distance, age and source non-uniformity. As a target phantom is younger, TEDE per cumulated activity significantly decreases with a smaller source distribution (e.g. thyroid), especially at a shorter distance. It might be incorrect to assume that the point source method is always valid for the thyroid source region. TEDE per cumulated activity for lying position TEDE per cumulated activity (msv MBq 21 h 21 )in the simulation of the lying scenario is presented in Table 2 for the three source distributions: thyroid, abdomen and whole body. The value from the point source method at a distance of 0.3 m is higher than our values by a factor of 26, 29 and 23 for thyroid, abdomen and whole body region source, respectively. It is attributable from ignoring partial lateral irradiation from the adult male phantom in lying position and internal shielding between two phantoms. On this basis, a licensee can provide the patient with more specific instructions. CONCLUSIONS The MC-based calculations were performed with the revised ORNL paediatric and adult phantoms as a function of distance and different distributions of 131 I activity within the adult male phantom. Maximum releasable administered activities in accordance with the regulatory limit of 5 msv TEDE, and TEDE per cumulated activity were explicitly calculated by using the tissue-weighting factor of ICRP Publication 60 and the organ doses instead of relying on the exposure rate constant used in the point source/target method. The results of this study indicate that the overestimation of TEDE per cumulated activity based on the point source/target method is.2-fold. Therefore, licensees can release the adult male patient who has been administered higher activity and even further, the total cost of the overall procedure can be reduced because of shorter time of hospitalisation. The values of TEDE per cumulated activity obtained by the point source/target method in the scenario of lying are higher than the MC-based values by a factor of up to 29. TEDE per cumulated activity to the paediatric phantoms shows strong age (height)-dependencies, which reveal that dosimetry for children should be separately considered instead of using adult phantoms as a substitute. In conclusion, on the basis of the results of this study, a licensee may use less conservative patientspecific release criteria and provide the patient and the family members with more practical guidelines. Future studies will invoke the use of the paediatric and adult male and female hybrid phantoms generated by the University of Florida and National Cancer Institute, which are more realistic than the stylised phantoms in terms of organ structures as well as body contour. REFERENCES 1. USNRC. Criteria for the release of individuals administered radioactive materials NRC. Final rule U.S. Nuclear Regulatory Commission (1997). 2. USNRC. Consolidated Guidance About Materials Licensees: Program-Specific Guidance about Medical Use Licenses U.S. Nuclear Regulatory Commission (2002). 3. Protection N. C. o. R., Measurements. Precautions in the management of patients who have received therapeutic amounts of radionuclides: recommendations. National Council on Radiation Protection and Measurements (1970). 4. Siegel, J. A., Marcus, C. S. and Sparks, R. B. Calculating the absorbed dose from radioactive patients: Page 8 of 9

10 the line-source versus point-source model. J. Nucl. Med. 43, 1241 (2002). 5. Sparks, R. B., Siegel, J. A. and Wahl, R. L. The need for better methods to determine release criteria for patients administered radioactive material. Health Phys. 75, 385 (1998). 6. de Carvalho, A. B. Jr, Hunt, J., Silva, A. X. and Garcia, F. Use of a voxel phantom as a source and a second voxel phantom as a target to calculate effective doses in individuals exposed to patients treated with 131I. J. Nucl. Med. Technol. 37, (2009). 7. de Carvalho, A. B. Jr, Stabin, M. G., Siegel, J. A. and Hunt, J. Comparison of point, line and volume dose calculations for exposure to nuclear medicine therapy patients. Health Phys. 100, 185 (2011). 8. Juweid, M. E. Radioimmunotherapy of B-cell non- Hodgkin s lymphoma: from clinical trials to clinical practice. J. Nucl. Med. 43, 1507 (2002). 9. Han, E. Y., Bolch, W. and Eckerman, K. Revisions to the ORNL series of adult and pediatric computational phantoms for use with the MIRD schema. Health Phys. 90, (2006). TEDE CALCULATION BY MONTE CARLO 10. Cristy, M. and Eckerman, K. F. Specific absorbed fractions of energy at various ages from internal photon sources. ORNL/TM-8381 Vol Oak Ridge National Laboratory (1987). 11. Bolch, W. E., Eckerman, K. F., Sgouros, G. and Thomas, S. R. MIRD Pamphlet No. 21: a generalized schema for radiopharmaceutical dosimetry standardization of nomenclature. J.Nucl.Med.50, 477 (2009). 12. ICRP recommendations of the International Commission Radiological Protection. ICRP publication 60. International Commission on Radiological Protection (1991). 13. Brown, F. MCNP A General Monte Carlo N-Particle Transport Code, Version 5 Los Alamos National Laboratory. (2003). 14. Mountford, P., O doherty, M., Forge, N., Jeffries, A. and Coakley, A. Radiation dose rates from adult patients undergoing nuclear medicine investigations. Nucl. Med. Commun. 12, 767 (1991). 15. Parthasarathy, K. L. and Crawford, E. S. Treatment of thyroid carcinoma: emphasis on high-dose 131I outpatient therapy. J.Nucl.Med.Technol.30, (2002) Page 9 of 9

A Real-Time Monte Carlo System for Internal Dose Evaluation Using an Anthropomorphic Phantom with Different Shapes of Tumors Inserted

A Real-Time Monte Carlo System for Internal Dose Evaluation Using an Anthropomorphic Phantom with Different Shapes of Tumors Inserted A Real-Time Monte Carlo System for Internal Dose Evaluation Using an Anthropomorphic Phantom with Different Shapes of Tumors Inserted J. Wu, S. J. Chang, B. J. Chang, I. J. Chen, J. H. Chiu Health Physics

More information

Summary of Patient Release after Radioiodine Therapy Research Review

Summary of Patient Release after Radioiodine Therapy Research Review Summary of Patient Release after Radioiodine Therapy Research Review Introduction This report provides a summary of the Office of Research (RES) staff s efforts to evaluate radiation exposure to members

More information

Standardization of Radiopharmaceutical Dosimetry

Standardization of Radiopharmaceutical Dosimetry Standardization of Radiopharmaceutical Dosimetry Jonathon A. Nye, PhD Department of Radiology and Imaging Sciences Emory University SEAAPM 2011 Myrtle Beach, SC Review of Dosimetry Nomenclature Dose Gray

More information

Impact of ICRP-89 Based Models on Dose Estimates for Radiopharmaceuticals and CT Exams. Stabin MG, Kost SD, Clark JH, Pickens DR, Price RR, Carver DE

Impact of ICRP-89 Based Models on Dose Estimates for Radiopharmaceuticals and CT Exams. Stabin MG, Kost SD, Clark JH, Pickens DR, Price RR, Carver DE Impact of ICRP-89 Based Models on Dose Estimates for Radiopharmaceuticals and CT Exams Stabin MG, Kost SD, Clark JH, Pickens DR, Price RR, Carver DE Vanderbilt University, Nashville, TN, USA Abstract New

More information

The Management of Imaging Procedure Dose Nuclear Medicine Dose Indices

The Management of Imaging Procedure Dose Nuclear Medicine Dose Indices The Management of Imaging Procedure Dose Nuclear Medicine Dose Indices Wesley E. Bolch, PhD, PE, DABHP, FHPS, FAAPM Director, Advanced Laboratory for Radiation Dosimetry Studies Department of Biomedical

More information

Sodium Iodide I 131 Solution. Click Here to Continue. Click Here to Return to Table of Contents

Sodium Iodide I 131 Solution. Click Here to Continue. Click Here to Return to Table of Contents Sodium Iodide I 131 Solution Package inserts are current as of January, 1997. Contact Professional Services, 1-888-744-1414, regarding possible revisions Click Here to Continue Click Here to Return to

More information

Figure 3. DS02 point-wise kerma coefficients (see Table 2) and DS02 fine group kerma coefficients (see Table 5) for photons in soft tissue.

Figure 3. DS02 point-wise kerma coefficients (see Table 2) and DS02 fine group kerma coefficients (see Table 5) for photons in soft tissue. 841 Figure 3. DS02 point-wise kerma coefficients (see Table 2) and DS02 fine group kerma coefficients (see Table 5) for photons in soft tissue. by a factor of two depending on whether the location was

More information

Citation for the original published paper (version of record):

Citation for the original published paper (version of record): http://www.diva-portal.org This is the published version of a paper published in EJNMMI Research. Citation for the original published paper (version of record): Andersson, M., Johansson, L., Eckerman,

More information

MONTE CARLO SIMULATIONS FOR HOMELAND SECURITY USING ANTHROPOMORPHIC PHANTOMS. A Thesis Presented to The Academic Faculty.

MONTE CARLO SIMULATIONS FOR HOMELAND SECURITY USING ANTHROPOMORPHIC PHANTOMS. A Thesis Presented to The Academic Faculty. MONTE CARLO SIMULATIONS FOR HOMELAND SECURITY USING ANTHROPOMORPHIC PHANTOMS A Thesis Presented to The Academic Faculty by Kimberly A Burns In Partial Fulfillment of the Requirements for the Degree Master

More information

3D Printed Phantoms for MRT Dosimetry

3D Printed Phantoms for MRT Dosimetry 3D Printed Phantoms for MRT Dosimetry Dr. Andrew Robinson Nuclear Physics Group, The University of Manchester Christie Medical Physics and Engineering, The Christie NHS Foundation Trust BIR/IDUG: The Future

More information

The estimated absorbed doses from a bolus intravenous

The estimated absorbed doses from a bolus intravenous BASIC SCIENCE INVESTIGATIONS MIRD Dose Estimate Report No. 19: Radiation Absorbed Dose Estimates from F-FDG Marguerite T. Hays, MD 1,2 ; Evelyn E. Watson, BA 3 ; Stephen R. Thomas, PhD 4 ; and Michael

More information

Study of the Influence of Radionuclide Biokinetic Distribution in Human Body on the Efficiency Response of Lung Counters

Study of the Influence of Radionuclide Biokinetic Distribution in Human Body on the Efficiency Response of Lung Counters Study of the nfluence of Radionuclide Biokinetic Distribution in Human Body on the Efficiency Response of Counters LU Liye 1, 2, *, CAO Qinjian 1, ZHAO Yuan 1, WE Xiaofeng 1, XAO Yunshi 1, XONG Wanchun

More information

Review of the radiological protection discharge protocol used in the treatment of thyroid cancer in the Virgen del Rocio University Hospitals

Review of the radiological protection discharge protocol used in the treatment of thyroid cancer in the Virgen del Rocio University Hospitals Review of the radiological protection discharge protocol used in the treatment of thyroid cancer in the Virgen del Rocio University Hospitals I. González 1, M. Herrador 1, J. R. Rodríguez 2, J. Carbajo

More information

Tracking Doses in the Pediatric Population

Tracking Doses in the Pediatric Population Tracking Doses in the Pediatric Population Frederic H. Fahey DSc Boston Children s Hospital Harvard Medical School frederic.fahey@childrens.harvard.edu Disclosures Sadly, none that pay me any money! SNMMI

More information

[Setawati et. al., Vol.4 (Iss10): October, 2017] ISSN: DOI: /zenodo

[Setawati et. al., Vol.4 (Iss10): October, 2017] ISSN: DOI: /zenodo EXTERNAL RADIATION SIMULATION OF LINAC TO DETERMINE EFFECTIVE DOSE IN ORGANS USING MONTE CARLO METHOD Evi Setawati *1, Muchammad Azam 1, Ngurah Ayu Ketut Umiati 1, Hammam Oktajianto 1 *1 Physics Department,

More information

Comparison of absorbed fraction of Gamma and Beta rays of I-124 and I-131radio-isotopes in thyroid gland with Monte Carlo Simulation

Comparison of absorbed fraction of Gamma and Beta rays of I-124 and I-131radio-isotopes in thyroid gland with Monte Carlo Simulation Available online at http://www.ijabbr.com International journal of Advanced Biological and Biomedical Research Volume 1, Issue 9, 2013: 993-998 Comparison of absorbed fraction of Gamma and Beta rays of

More information

Application of 3D Printing to Molecular Radiotherapy Phantoms. Nick Calvert Nuclear Medicine Group The Christie NHS Foundation Trust, Manchester

Application of 3D Printing to Molecular Radiotherapy Phantoms. Nick Calvert Nuclear Medicine Group The Christie NHS Foundation Trust, Manchester Application of 3D Printing to Molecular Radiotherapy Phantoms Nick Calvert Nuclear Medicine Group The Christie NHS Foundation Trust, Manchester Molecular Radiotherapy Radionuclide administered to patient

More information

Organ Dose Variability with Gender, Age and BMI

Organ Dose Variability with Gender, Age and BMI Organ Dose Variability with Gender, Age and BMI Dr Ted Lazo CRPPH Scientific Secretariat Article 31 Meeting, 17 May 2017, Luxembourg Background The ICRP system uses a generalised, gender and age averaged

More information

Patient effective dose evaluation for chest X-ray examination in three digital radiography centers

Patient effective dose evaluation for chest X-ray examination in three digital radiography centers Patient effective dose evaluation for chest X-ray examination in three digital radiography centers R. Paydar 1,3*, A. Takavar 1, M.R. Kardan 2,3, A. Babakhani 3,4, M.R. Deevband 3, S. Saber 5 1Medical

More information

ICRP Perspective on Internal Dosimetry OIR and Radiopharmaceuticals

ICRP Perspective on Internal Dosimetry OIR and Radiopharmaceuticals ICRP Perspective on Internal Dosimetry OIR and Radiopharmaceuticals Dietmar Noßke dnosske@web.de 1 Disclaimer The information and views set out in this presentation are those of the author and do not necessarily

More information

Use Of MCNP With Voxel-Based Image Data For Internal Dosimetry Applications

Use Of MCNP With Voxel-Based Image Data For Internal Dosimetry Applications Use Of MCNP With Voxel-Based Image Data For Internal Dosimetry Applications The Monte Carlo Method: Versatility Unbounded In A Dynamic Computing World Chattanooga, TN, USA, April 17-21, 2005 M. G. Stabin

More information

Dollars and Sense: Are We Overshielding Imaging Facilities? Part 2

Dollars and Sense: Are We Overshielding Imaging Facilities? Part 2 Disclosure Dollars and Sense: Are We Overshielding Imaging Facilities? Part 2 Bryon M. Murray, M.S., DABR Paid consultant to NELCO Worldwide Owner, CEO ZapIT! Medical Objectives Understand methods for

More information

EVALUATION OF INTERNAL CONTAMINATION LEVELS AFTER A RADIOLOGICAL DISPERSAL DEVICE USING PORTAL MONITORS. A Thesis Presented to The Academic Faculty

EVALUATION OF INTERNAL CONTAMINATION LEVELS AFTER A RADIOLOGICAL DISPERSAL DEVICE USING PORTAL MONITORS. A Thesis Presented to The Academic Faculty EVALUATION OF INTERNAL CONTAMINATION LEVELS AFTER A RADIOLOGICAL DISPERSAL DEVICE USING PORTAL MONITORS A Thesis Presented to The Academic Faculty by Randahl Christelle Palmer In Partial Fulfillment of

More information

Dose Estimates for Nuclear Medicine Procedures: What are they? Where do they come from?

Dose Estimates for Nuclear Medicine Procedures: What are they? Where do they come from? Dose Estimates for Nuclear Medicine Procedures: What are they? Where do they come from? SNM Continuing Education Lecture Salt Lake City, UT -- June 6, 2010 Darrell R. Fisher Pacific Northwest National

More information

ICRP-ERPW Symposium. Paris, October10-12, Chan Hyeong Kim Hanyang University

ICRP-ERPW Symposium. Paris, October10-12, Chan Hyeong Kim Hanyang University ICRP-ERPW Symposium Paris, October10-12, 2017 Chan Hyeong Kim Hanyang University * Contributing Authors: YS Yeom, TT Nguyen, MC Han, CS Choi, H Lee, H Han, B Shin, J-K. Lee, HS Kim, M Zankl, N Petoussi-Henss,

More information

Nuclear Regulatory Commission guidance on release of radioactive patients

Nuclear Regulatory Commission guidance on release of radioactive patients Nuclear Regulatory Commission guidance on release of radioactive patients Dawn Banghart, CHP Sr. Health Physicist Alt. Radiation Safety Officer Nuc Med Can this therapy patient be released? Lu 177 Radioactive

More information

Internal Dosimetry of Human Brain for 99m tc and 131 I Using Nuclear Imaging in Bangladesh

Internal Dosimetry of Human Brain for 99m tc and 131 I Using Nuclear Imaging in Bangladesh Sri Lankan Journal of Physics, Vol. 6 (2005) 33-41 Institute of Physics - Sri Lanka Internal Dosimetry of Human Brain for 99m tc and 131 I Using Nuclear Imaging in Bangladesh M. M. Alam a, M. I. Kabir

More information

Overview of ICRP Committee 2 Doses from Radiation Exposure

Overview of ICRP Committee 2 Doses from Radiation Exposure Overview of ICRP Committee 2 Doses from Radiation Exposure J. Harrison Public Health England, Centre for Radiation, Chemical and Environmental Hazards, Chilton, Didcot, Oxon OX11 0RQ, UK; e-mail: john.harrison@phe.gov.uk

More information

Radiopharmaceuticals used in diagnostic and therapeutic

Radiopharmaceuticals used in diagnostic and therapeutic MIRD Pamphlet No. 19: Absorbed Fractions and Radionuclide S Values for Six Age-Dependent Multiregion Models of the Kidney* Lionel G. Bouchet, PhD 1, ; Wesley E. Bolch, PhD,3 ; H. Pablo Blanco, MS 3 ; Barry

More information

Figure 1.1 PHITS geometry for PTB irradiations with: broad beam, upper panel; mono energetic beams, lower panel. Pictures of the setups and of the

Figure 1.1 PHITS geometry for PTB irradiations with: broad beam, upper panel; mono energetic beams, lower panel. Pictures of the setups and of the Figure 1.1 PHITS geometry for PTB irradiations with: broad beam, upper panel; mono energetic beams, lower panel. Pictures of the setups and of the PMMA ring holder with 7 containers are also shown. Relative

More information

Simulations and measurements of radiation doses from patients treated with I-131

Simulations and measurements of radiation doses from patients treated with I-131 UMEÅ UNIVERSITY Department of Radiation Sciences Master thesis 30 hp April 13, 2018 Daniel Gälman Master s thesis in radiation sciences Simulations and measurements of radiation doses from patients treated

More information

A REVISED MODEL FOR DOSIMETRY IN THE HUMAN SMALL INTESTINE. Final Progress Report

A REVISED MODEL FOR DOSIMETRY IN THE HUMAN SMALL INTESTINE. Final Progress Report A REVISED MODEL FOR DOSIMETRY IN THE HUMAN SMALL INTESTINE Final Progress Report Submitted by: John W. Poston, Sr., Professor Nasir U. Bhuiyan R. Alex Redd Neil D. Parham Jennifer A. Watson Department

More information

Click Here to Continue. Click Here to Return to Table of Contents

Click Here to Continue. Click Here to Return to Table of Contents Hippuran I 131 Injection Package inserts are current as of January, 1997. Contact Professional Services, 1-888-744-1414, regarding possible revisions Click Here to Continue Click Here to Return to Table

More information

Comparison of organ doses estimations in radiology with PCXMC application based on MIRD phantoms and CALDose-X application based on voxel phantoms

Comparison of organ doses estimations in radiology with PCXMC application based on MIRD phantoms and CALDose-X application based on voxel phantoms Comparison of organ doses estimations in radiology with PCXMC application based on MIRD phantoms and CALDose-X application based on voxel phantoms G. Gialousis 1, Z. Pappouli 2, A. Dimitriadis 2, E. Karavassilis

More information

STANDARDIZED RADIOGENIC CANCER RISK COEFFICIENTS: A REVIEW OF THE METHODOLOGY PRESENTED IN FEDERAL GUIDANCE REPORT NO. 13

STANDARDIZED RADIOGENIC CANCER RISK COEFFICIENTS: A REVIEW OF THE METHODOLOGY PRESENTED IN FEDERAL GUIDANCE REPORT NO. 13 STANDARDIZED RADIOGENIC CANCER RISK COEFFICIENTS: A REVIEW OF THE METHODOLOGY PRESENTED IN FEDERAL GUIDANCE REPORT NO. 13 ABSTRACT Michael Boyd and Christopher Nelson, U.S. Environmental Protection, Office

More information

Radiation Doses in Radiology: Influence of Standards and Regulations

Radiation Doses in Radiology: Influence of Standards and Regulations Radiation Doses in Radiology: Influence of Standards and Regulations Beebe Symposium National Academy of Sciences December 9, 2009 Washington D.C. Orhan H Suleiman MS PhD, FAAPM Senior Science Policy Adviser

More information

Release of Patients or Human Research Subjects Administered Radioactive Materials

Release of Patients or Human Research Subjects Administered Radioactive Materials Release of Patients or Human Research Subjects Administered Radioactive Materials Section (41) (a), "Release of Individuals Containing Radioactive Drugs or Implants," of Chapter 420-3-26 of the Rules published

More information

Click Here to Continue. Click Here to Return to Table of Contents

Click Here to Continue. Click Here to Return to Table of Contents TechneScan Gluceptate Package inserts are current as of January, 1997. Contact Professional Services, 1-888-744-1414, regarding possible revisions. Click Here to Continue Click Here to Return to Table

More information

NUREG 1556-based Release of Patients from Radiation Safety Restrictions

NUREG 1556-based Release of Patients from Radiation Safety Restrictions CFR 5.75 NUREG 556-based Release of Patients from Radiation Safety Restrictions Richard E. Wendt III Department of Imaging Physics UT M. D. Anderson Cancer Center Houston, Texas 77 A patient who has been

More information

Impact of ICRP-89 Based Models on Dose Estimates for Radiopharmaceuticals and CT Exams

Impact of ICRP-89 Based Models on Dose Estimates for Radiopharmaceuticals and CT Exams Impact of ICRP-89 Based Models on Dose Estimates for Radiopharmaceuticals and CT Exams Stabin MG, Kost SD, Clark JH, Pickens DR, Price RR, Carver DE Vanderbilt University Nashville, TN, USA 13th International

More information

FAX, A FEMALE ADULT VOXEL PHANTOM FOR RADIATION PROTECTION DOSIMETRY

FAX, A FEMALE ADULT VOXEL PHANTOM FOR RADIATION PROTECTION DOSIMETRY EFFECTIVE DOSE RATIOS FOR THE TOMOGRAPHIC MAX AND FAX PHANTOMS ******************************************************** EFFECTIVE DOSE RATIOS FOR TOMOGRAPHIC AND STYLIZED MODELS FROM > EXTERNAL EXPOSURE

More information

Calculation of Normalised Organ and Effective Doses to Adult Reference Computational Phantoms from Contemporary Computed Tomography Scanners

Calculation of Normalised Organ and Effective Doses to Adult Reference Computational Phantoms from Contemporary Computed Tomography Scanners Progress in NUCLEAR SCIENCE and TECHNOLOGY, Vol. 2, pp.165-171 (2011) ARTICLE Calculation of Normalised Organ and Effective Doses to Adult Reference Computational Phantoms from Contemporary Computed Tomography

More information

Mohd Fahmi MY*, Norsuriani S and Abdullah Waidi I. School of Health Sciences, UniversitiSains Malaysia, Kota Bharu, Kelantan, Malaysia.

Mohd Fahmi MY*, Norsuriani S and Abdullah Waidi I. School of Health Sciences, UniversitiSains Malaysia, Kota Bharu, Kelantan, Malaysia. Estimation of Exposure Rate to Personnel Working in Nuclear Medicine Imaging Department in Hospital Universiti Sains Malaysia: Comparison between Direct and Indirect Methods Mohd Fahmi MY*, Norsuriani

More information

GALLIUM CITRATE Ga 67 INJECTION

GALLIUM CITRATE Ga 67 INJECTION 511945-0903 September 2003 USA Bristol-Myers Squibb Medical Imaging 331 Treble Cove Road N. Billerica, MA 01862 USA GALLIUM CITRATE Ga 67 INJECTION FOR DIAGNOSTIC USE DESCRIPTION: Gallium Citrate Ga 67

More information

Introduction. Chapter 15 Radiation Protection. Advisory bodies. Regulatory bodies. Main Principles of Radiation Protection

Introduction. Chapter 15 Radiation Protection. Advisory bodies. Regulatory bodies. Main Principles of Radiation Protection Introduction Chapter 15 Radiation Protection Radiation Dosimetry I Text: H.E Johns and J.R. Cunningham, The physics of radiology, 4 th ed. F.M. Khan, The Physics of Radiation Therapy, 4th ed., Chapter

More information

Optimization of a routine method for bone marrow dose estimation in

Optimization of a routine method for bone marrow dose estimation in Optimization of a routine method for bone marrow dose estimation in 177 Lu-EDTMP therapy- Experience in Uruguay. Teran. M 1, Paolino.A 2, Coppe.F 2, Nuñez M 2, Hermida J C 2, Gaudiano.J 2 1 Cátedra de

More information

Regulatory Guidelines and Computational Methods for Safe Release of Radioactive Patients II. Brachytherapy

Regulatory Guidelines and Computational Methods for Safe Release of Radioactive Patients II. Brachytherapy Regulatory Guidelines and Computational Methods for Safe Release of Radioactive Patients II. Brachytherapy Firas Mourtada, Ph.D., DABR Chief of Clinical Physics Helen F. Graham Cancer Center Christiana

More information

ICRP Recommendations Evolution or Revolution? John R Cooper Main Commission

ICRP Recommendations Evolution or Revolution? John R Cooper Main Commission ICRP Recommendations Evolution or Revolution? John R Cooper Main Commission 3 September 2009 ICRP Recommendations 1. Reasons for new Recommendations 2. Summary of health risks 3. Summary of changes to

More information

GLUCEPTATE. Technetium Tc 99m Gluceptate Kit DIAGNOSTIC DESCRIPTION

GLUCEPTATE. Technetium Tc 99m Gluceptate Kit DIAGNOSTIC DESCRIPTION 27194 0001E m TM GLUCEPTATE Technetium Tc 99m Gluceptate Kit DIAGNOSTIC DESCRIPTION The kit consists of reaction vials which contain the sterile, non-pyrogenic, nonradioactive ingredients necessary to

More information

Journal of Radiation Research and Applied Sciences 8 (2015) 317e322. Available online at ScienceDirect

Journal of Radiation Research and Applied Sciences 8 (2015) 317e322. Available online at  ScienceDirect Journal of Radiation Research and Applied Sciences 8 (2015) 317e322 HOSTED BY Available online at www.sciencedirect.com ScienceDirect Journal of Radiation Research and Applied Sciences journal homepage:

More information

Skyscan 1076 in vivo scanning: X-ray dosimetry

Skyscan 1076 in vivo scanning: X-ray dosimetry Skyscan 1076 in vivo scanning: X-ray dosimetry DOSIMETRY OF HIGH RESOLUTION IN VIVO RODENT MICRO-CT IMAGING WITH THE SKYSCAN 1076 An important distinction is drawn between local tissue absorbed dose in

More information

GUIDELINES ON IONISING RADIATION DOSE LIMITS AND ANNUAL LIMITS ON INTAKE OF RADIOACTIVE MATERIAL

GUIDELINES ON IONISING RADIATION DOSE LIMITS AND ANNUAL LIMITS ON INTAKE OF RADIOACTIVE MATERIAL RADIATION PROTECTION AUTHORITY OF ZIMBABWE (RPAZ) RADIATION PROTECTION ACT [CHAPTER 15:15] GUIDELINES ON IONISING RADIATION DOSE LIMITS AND ANNUAL LIMITS ON INTAKE OF RADIOACTIVE MATERIAL Compiled by Radiation

More information

Quantitative Theranostics in Nuclear Medicine

Quantitative Theranostics in Nuclear Medicine Quantitative Theranostics in Nuclear Medicine M. Lassmann Klinik und Poliklinik für Nuklearmedizin Direktor: Prof. Dr. A. Buck Contents What is Theranostics? Potential Targets Basic Principles of Quantitative

More information

MICRODOSIMETRY CALCULATION OF THE DOSE CONVERSION COEFFICIENT FOR RADON PROGENY. B.M.F. Lau, D. Nikezic, K.N. Yu

MICRODOSIMETRY CALCULATION OF THE DOSE CONVERSION COEFFICIENT FOR RADON PROGENY. B.M.F. Lau, D. Nikezic, K.N. Yu MICRODOSIMETRY CALCULATION OF THE DOSE CONVERSION COEFFICIENT FOR RADON PROGENY B.M.F. Lau, D. Nikezic, K.N. Yu Department of Physics and Materials Science, City University of Hong Kong, Tat Chee Avenue,

More information

Radiation Protection Program Update: The Details. July 2010

Radiation Protection Program Update: The Details. July 2010 Radiation Protection Program Update: The Details July 2010 Update Topics 2 Changes mandated by Title 10, Code of Federal Regulations, Part 835, Occupational Radiation Protection (10 CFR 835) How changes

More information

A 3D CANINE HYBRID PHANTOM AND SOFTWARE FOR RADIOPHARMACEUTICAL THERAPY DOSIMETRY

A 3D CANINE HYBRID PHANTOM AND SOFTWARE FOR RADIOPHARMACEUTICAL THERAPY DOSIMETRY A 3D CANINE HYBRID PHANTOM AND SOFTWARE FOR RADIOPHARMACEUTICAL THERAPY DOSIMETRY By LAURA PADILLA A DISSERTATION PRESENTED TO THE GRADUATE SCHOOL OF THE UNIVERSITY OF FLORIDA IN PARTIAL FULFILLMENT OF

More information

Health Concerns Related to Radiation Exposure. of the Female Nuclear Medicine Patient. Michael G. Stabin

Health Concerns Related to Radiation Exposure. of the Female Nuclear Medicine Patient. Michael G. Stabin Health Concerns Related to Radiation Exposure of the Female Nuclear Medicine Patient Michael G. Stabin Radiation Internal Dose Information Center Oak Ridge Institute for Science and Education P.O. Box

More information

Downloaded from by guest on 18 November 2018

Downloaded from   by guest on 18 November 2018 Radiation Protection Dosimetry Vol. 105, No. 1 4, pp. 581 586 (2003) Published by Nuclear Technology Publishing 2003 Nuclear Technology Publishing ASSESSMENTS FOR HIGH DOSE RADIONUCLIDE THERAPY TREATMENT

More information

Adult: > 18 Years ALARA: As low as reasonably achievable ALI:

Adult: > 18 Years ALARA: As low as reasonably achievable ALI: Health Physics Adult: > 18 Years ALARA: As low as reasonably achievable ALI: Annual Limit on Intake. The amount of an isotope that if taken into the body over the course of a year would result in in a

More information

Development of Hybrid Newborn Computational Phantom for Dosimetry Calculation: The Skeleton

Development of Hybrid Newborn Computational Phantom for Dosimetry Calculation: The Skeleton Development of Hybrid Newborn Computational Phantom for Dosimetry Calculation: The Skeleton Deanna Hasenauer*, M.Sc., Ph.D. Candidate Department of University of Florida Gainesville, FL *DOE Health Physics

More information

Third announcement. Joint FMU-ICRP Workshop on Radiological Protection in Medicine. Tuesday, October 3, 2017

Third announcement. Joint FMU-ICRP Workshop on Radiological Protection in Medicine. Tuesday, October 3, 2017 ICRP ref: 4852-9144-9932 Third announcement Joint FMU-ICRP Workshop on Radiological Protection in Medicine Tuesday, October 3, 2017 Organised by Fukushima Medical University (FMU) and the International

More information

Radiation Dose Rates from Patients Administrated Radiopharmaceuticals Used for Brain Blood Flow Investigation.

Radiation Dose Rates from Patients Administrated Radiopharmaceuticals Used for Brain Blood Flow Investigation. Radiation Dose Rates from Patients Administrated Radiopharmaceuticals Used for Brain Blood Flow Investigation K.Ejiri 1, K. Minami 1, T.Sawai 3, M.Kato 3, K.Kikukawa 2, H.Toyama 2, T. Orito 1 and S. Koga

More information

Calculation methods in Hermes Medical Solutions dosimetry software

Calculation methods in Hermes Medical Solutions dosimetry software Calculation methods in Hermes Medical Solutions dosimetry software Helena McMeekin MSc. Clinical Applications Scientist, Hermes Medical Solutions MRTDosimetry Scientific Workshop The Principals and Clinical

More information

DRAXIMAGE SODIUM IODIDE I 131 CAPSULES, USP DIAGNOSTIC. For Oral Use DESCRIPTION

DRAXIMAGE SODIUM IODIDE I 131 CAPSULES, USP DIAGNOSTIC. For Oral Use DESCRIPTION DRAXIMAGE SODIUM IODIDE I 131 CAPSULES, USP DIAGNOSTIC For Oral Use DESCRIPTION Sodium Iodide I 131 Capsules, USP are color-coded capsules containing sodium iodide I 131 for diagnostic use by oral administration.

More information

DRAXIMAGE SODIUM IODIDE I 131 SOLUTION USP DIAGNOSTIC. For Oral Use DESCRIPTION

DRAXIMAGE SODIUM IODIDE I 131 SOLUTION USP DIAGNOSTIC. For Oral Use DESCRIPTION DRAXIMAGE SODIUM IODIDE I 131 SOLUTION USP DIAGNOSTIC For Oral Use DESCRIPTION Sodium Iodide I 131 Solution is an aqueous solution of sodium iodide I-131 for diagnostic use by oral administration. The

More information

Use of Bubble Detectors to Characterize Neutron Dose Distribution in a Radiotherapy Treatment Room used for IMRT treatments

Use of Bubble Detectors to Characterize Neutron Dose Distribution in a Radiotherapy Treatment Room used for IMRT treatments Use of Bubble Detectors to Characterize Neutron Dose Distribution in a Radiotherapy Treatment Room used for IMRT treatments Alana Hudson *1 1 Tom Baker Cancer Centre, Department of Medical Physics, 1331

More information

Uncertainties on internal dosimetry

Uncertainties on internal dosimetry Uncertainties on internal dosimetry Augusto Giussani 2 March 2017 agiussani@bfs.de Internal dosimetry Internal dose is evaluated with mathematical models Intake Biokinetic Model Time-activity curves in

More information

Clinical Implementation of patient-specific dosimetry, comparison with absorbed fraction-based method

Clinical Implementation of patient-specific dosimetry, comparison with absorbed fraction-based method Clinical Implementation of patient-specific dosimetry, comparison with absorbed fraction-based method George Sgouros, Ph.D. Russell H. Morgan Dept of Radiology & Radiological Science Johns Hopkins University,

More information

Site Planning and Design of PET/CT Facilities. Melissa C. Martin, M.S., FACR, FAAPM AAPM Annual Meeting, Orlando, FL August 2, 2006

Site Planning and Design of PET/CT Facilities. Melissa C. Martin, M.S., FACR, FAAPM AAPM Annual Meeting, Orlando, FL August 2, 2006 Site Planning and Design of PET/CT Facilities Melissa C. Martin, M.S., FACR, FAAPM AAPM Annual Meeting, Orlando, FL August 2, 2006 Acknowledgements: AAPM Task Group #108 on PET and PET/CT Shielding Requirements

More information

Radiation Protection Principles for Radioiodine Therapy

Radiation Protection Principles for Radioiodine Therapy Strahlenschutzkommission Geschäftsstelle der Strahlenschutzkommission Postfach 12 06 29 D-53048 Bonn http://www.ssk.de Radiation Protection Principles for Radioiodine Therapy Recommendation by the German

More information

Dosimetry (Dose Estimation) of Internal Emitters. Outline. For Radiation Effects, is Dose the only Answer? Estimation of Dose and not Dosimetry

Dosimetry (Dose Estimation) of Internal Emitters. Outline. For Radiation Effects, is Dose the only Answer? Estimation of Dose and not Dosimetry Dosimetry (Dose Estimation) of Internal Emitters. Lawrence E. Williams, PhD City of Hope National Medical Center Duarte CA 91010 lwilliams@coh.org Outline 1. Dose Estimation Formula D = S*Ã 2. Determination

More information

Medical Physics 4 I3 Radiation in Medicine

Medical Physics 4 I3 Radiation in Medicine Name: Date: 1. This question is about radiation dosimetry. Medical Physics 4 I3 Radiation in Medicine Define exposure. A patient is injected with a gamma ray emitter. The radiation from the source creates

More information

Dosimetry Optimization System and Integrated Software (DOSIS): a comparison against Fluka code results over a standard phantom

Dosimetry Optimization System and Integrated Software (DOSIS): a comparison against Fluka code results over a standard phantom Dosimetry Optimization System and Integrated Software (DOSIS): a comparison against Fluka code results over a standard phantom Institute of Physics E. Gaviola - CONICET & LIIFAMIRX - Laboratorio de Investigación

More information

Annex V of Technical Volume 4 UNSCEAR ASSESSMENT OF THE DOSE TO THE PUBLIC

Annex V of Technical Volume 4 UNSCEAR ASSESSMENT OF THE DOSE TO THE PUBLIC Annex V of Technical Volume 4 UNSCEAR ASSESSMENT OF THE DOSE TO THE PUBLIC V 1. UNSCEAR ASSESSMENT OF EXTERNAL EXPOSURE V 1.1. External exposure during passage of the plume There were not enough environmental

More information

State of the art and future development for standardized estimation of organ doses in CT

State of the art and future development for standardized estimation of organ doses in CT State of the art and future development for standardized estimation of organ doses in CT March 2015 William J. O Connel, Dr. Ph, Senior Medical Physicist Imagination at work. Agenda Introduction Duke Florida

More information

PHYSICS 2: HSC COURSE 2 nd edition (Andriessen et al) CHAPTER 20 Radioactivity as a diagnostic tool (pages 394-5)

PHYSICS 2: HSC COURSE 2 nd edition (Andriessen et al) CHAPTER 20 Radioactivity as a diagnostic tool (pages 394-5) PHYSICS 2: HSC COURSE 2 nd edition (Andriessen et al) CHAPTER 20 Radioactivity as a diagnostic tool (pages 394-5) 1. (a) A radioisotope is an isotope that is unstable and will emit particles from the nucleus

More information

Internal Doslmetry in Nuclear Medicine: A Summary of its Development, Applications and Current Limitations

Internal Doslmetry in Nuclear Medicine: A Summary of its Development, Applications and Current Limitations Internal Doslmetry in Nuclear Medicine: A Summary of its Development, Applications and Current Limitations by M. Lyra and P. Phinou Introduction In this article, a historical presentation of the development

More information

Radiation Safety for New Medical Physics Graduate Students

Radiation Safety for New Medical Physics Graduate Students Radiation Safety for New Medical Physics Graduate Students John Vetter, PhD Medical Physics Department UW School of Medicine & Public Health Background and Purpose of This Training This is intended as

More information

Inpatient Admission for Radiation Therapy

Inpatient Admission for Radiation Therapy Medical Coverage Policy Effective Date... 8/15/2017 Next Review Date... 8/15/2018 Coverage Policy Number... 0408 Inpatient Admission for Radiation Therapy Table of Contents Coverage Policy... 1 Overview...

More information

Recent Progress in Radiation Dosimetry for Epidemiology and Radiological Protection. John Harrison ICRP Committee 2

Recent Progress in Radiation Dosimetry for Epidemiology and Radiological Protection. John Harrison ICRP Committee 2 Recent Progress in Radiation Dosimetry for Epidemiology and Radiological Protection John Harrison ICRP Committee 2 Joint ICRP-RERF-JHPS Workshop: Tokyo, December 2017 Task Group 79 : Use of Effective Dose

More information

Increased Radiation Dose to Overweight and Obese Patients from Radiographic Examinations

Increased Radiation Dose to Overweight and Obese Patients from Radiographic Examinations Increased Radiation Dose to Overweight and Obese Patients from Radiographic Examinations The MIT Faculty has made this article openly available. Please share how this access benefits you. Your story matters.

More information

Assessment of effective dose in paediatric CT examinations

Assessment of effective dose in paediatric CT examinations Assessment of effective dose in paediatric CT examinations E. Dougeni 1,2 CL. Chapple 1, J. Willis 1, G. Panayiotakis 2 1 Regional Medical Physics Department, Freeman Hospital, Freeman Road, Newcastle

More information

Application of the Commission's Recommendations for the Protection of People in

Application of the Commission's Recommendations for the Protection of People in ICRP Publication 127 ICRP Publication 126 ICRP Publication 125 ICRP Publication 124 ICRP Publication 123 ICRP Publication 122 ICRP Publication 121 ICRP Publication 120 ICRP 2011 Proceedings Radiological

More information

PHY138Y Nuclear and Radiation

PHY138Y Nuclear and Radiation PHY38Y Nuclear and Radiation Professor Tony Key MP40 key@physics.utoronto.ca Announcements MP problems set #4 due Sunday at midnight PS#5 WRITTEN now posted! - do in teams, no Lone Wolves!! NB correction

More information

R: March, E D T P A. Kit for the Preparation of Technetium Tc 99m Pentetate Injection. DIAGNOSTIC - For Intravenous Use

R: March, E D T P A. Kit for the Preparation of Technetium Tc 99m Pentetate Injection. DIAGNOSTIC - For Intravenous Use R: March, 1998 27227 0002E m TM DESCRIPTION D T P A Kit for the Preparation of Technetium Tc 99m Pentetate Injection DIAGNOSTIC - For Intravenous Use Each kit consists of reaction vials which contain the

More information

ICRP 128 ICRP ICRP ICRP 1928

ICRP 128 ICRP ICRP ICRP 1928 ICRP 1928 129 ICRP 1928 ICRP ICRP ICRP 1928 129 ICRP 129 ICRP 128 Radiological Protection in Cone Beam Computed Tomography (CBCT) Radiation Dose to Patients from Radiopharmaceuticals: A Compendium of Current

More information

Individualised Treatment Planning for Radionuclide therapy (Molecular Radiotherapy)

Individualised Treatment Planning for Radionuclide therapy (Molecular Radiotherapy) Individualised Treatment Planning for Radionuclide therapy (Molecular Radiotherapy) FMU/ICRP workshop 2017 Glenn Flux Royal Marsden Hospital & Institute of Cancer Research Sutton UK ICRP Task Group 101

More information

Nuclear Medicine and PET. D. J. McMahon rev cewood

Nuclear Medicine and PET. D. J. McMahon rev cewood Nuclear Medicine and PET D. J. McMahon 150504 rev cewood 2018-02-15 Key Points Nuclear Medicine and PET: Imaging: Understand how Nuc Med & PET differ from Radiography & CT by the source of radiation. Be

More information

Measurement of organ dose in abdomen-pelvis CT exam as a function of ma, KV and scanner type by Monte Carlo method

Measurement of organ dose in abdomen-pelvis CT exam as a function of ma, KV and scanner type by Monte Carlo method Iran. J. Radiat. Res., 2004; 1(4): 187-194 Measurement of organ dose in abdomen-pelvis CT exam as a function of ma, KV and scanner type by Monte Carlo method M.R. Ay 1, M. Shahriari 2, S. Sarkar 3, P.

More information

Radiation Safety Information for Students in Courses given by the Nuclear Physics Group at KTH, Stockholm, Sweden

Radiation Safety Information for Students in Courses given by the Nuclear Physics Group at KTH, Stockholm, Sweden Radiation Safety Information for Students in Courses given by the Nuclear Physics Group at KTH, Stockholm, Sweden September 2006 The aim of this text is to explain some of the basic quantities and units

More information

How to assess doses from internal emitters

How to assess doses from internal emitters How to assess doses from internal emitters in Radiation Protection and Medicine PD Dr. Bastian Breustedt, Safety and Environment (SUM) KIT Die Forschungsuniversität in der Helmholtz-Gemeinschaft www.kit.edu

More information

Cigna Medical Coverage Policy

Cigna Medical Coverage Policy Cigna Medical Coverage Policy Subject Inpatient Admission for Radiation Therapy Table of Contents Coverage Policy... 1 General Background... 1 Coding/Billing Information... 3 References... 3 Effective

More information

Assessment of radiation risk to pediatric patients undergoing conventional X-ray examinations

Assessment of radiation risk to pediatric patients undergoing conventional X-ray examinations Radioprotection 50(1), 19-25 (2015) c EDP Sciences 2015 DOI: 10.1051/radiopro/2014023 Available online at: www.radioprotection.org Article Assessment of radiation risk to pediatric patients undergoing

More information

PERSONNEL MONITORING AND DOSIMETRY POLICIES

PERSONNEL MONITORING AND DOSIMETRY POLICIES PERSONNEL MONITORING AND DOSIMETRY POLICIES All individuals who are required to have their exposure to ionizing radiation monitored must be trained prior to using the source(s) of radiation. The radioactive

More information

PHYSICAL CHARACTERISTICS

PHYSICAL CHARACTERISTICS BRACCO DIAGNOSTICS L/4739/0 1 CHOLETEC Kit for the Preparation of Technetium Tc 99m Mebrofenin For Diagnostic Use DESCRIPTION Each reaction vial contains a nonradioactive, sterile, nonpyrogenic mixture

More information

Targeted Alpha Particle Therapy: Imaging, Dosimetry and Radiation Protection

Targeted Alpha Particle Therapy: Imaging, Dosimetry and Radiation Protection Targeted Alpha Particle Therapy: Imaging, Dosimetry and Radiation Protection Michael Lassmann Klinik und Poliklinik für Nuklearmedizin Direktor: Prof. Dr. A. Buck Targeted Therapy Basic Principles 2 Influence

More information

CT Dose Estimation. John M. Boone, Ph.D., FAAPM, FSBI, FACR Professor and Vice Chair of Radiology. University of California Davis Medical Center

CT Dose Estimation. John M. Boone, Ph.D., FAAPM, FSBI, FACR Professor and Vice Chair of Radiology. University of California Davis Medical Center CT Dose Estimation John M. Boone, Ph.D., FAAPM, FSBI, FACR Professor and Vice Chair of Radiology 1 University of California Davis Medical Center CT Dose Estimation Introduction The CTDI Family of Metrics

More information

Background Radiation in U.S. ~ msv/yr msv/yr ~0.02 ~0.02 msv msv/day /day (~2 m rem/day) mrem/day) NCRP 4

Background Radiation in U.S. ~ msv/yr msv/yr ~0.02 ~0.02 msv msv/day /day (~2 m rem/day) mrem/day) NCRP 4 Patient Safety Concerns in Diagnostic Radiology? Lawrence T. Dauer, PhD, CHP Assistant Attending Health Physicist Department of Medical Physics RAMPS/GNYCHPS Spring Symposium April 30, 2010 Benefits?

More information

EQUIVALENT DOSE FROM SECONDARY NEUTRONS AND SCATTER PHOTONS IN ADVANCE RADIATION THERAPY TECHNIQUES WITH 15 MV PHOTON BEAMS

EQUIVALENT DOSE FROM SECONDARY NEUTRONS AND SCATTER PHOTONS IN ADVANCE RADIATION THERAPY TECHNIQUES WITH 15 MV PHOTON BEAMS PAPER EQUIVALENT DOSE FROM SECONDARY NEUTRONS AND SCATTER PHOTONS IN ADVANCE RADIATION THERAPY TECHNIQUES WITH 15 MV PHOTON BEAMS Isra Israngkul Na Ayuthaya *, Sivalee Suriyapee, Phongpheath Pengvanich

More information