IDAC-Dose 2.1, an Internal Dosimetry Program for Diagnostic Nuclear

Total Page:16

File Type:pdf, Size:1020Kb

IDAC-Dose 2.1, an Internal Dosimetry Program for Diagnostic Nuclear View metadata, citation and similar papers at core.ac.uk brought to you by CORE provided by Crossref Andersson et al. EJNMMI Research (2017) 7:88 DOI 10.1186/s13550-017-0339-3 ORIGINAL RESEARCH Open Access IDAC-Dose 2.1, an internal dosimetry program for diagnostic nuclear medicine based on the ICRP adult reference voxel phantoms Martin Andersson1* , Lennart Johansson2, Keith Eckerman3 and Sören Mattsson1 Abstract Background: To date, the estimated radiation-absorbed dose to organs and tissues in patients undergoing diagnostic examinations in nuclear medicine is derived via calculations based on models of the human body and the biokinetic behaviour of the radiopharmaceutical. An internal dosimetry computer program, IDAC-Dose2.1, was developed based on the International Commission on Radiological Protection (ICRP)-specific absorbed fractions and computational framework of internal dose assessment given for reference adults in ICRP Publication 133. The program uses the radionuclide decay database of ICRP Publication 107 and considers 83 different source regions irradiating 47 target tissues, defining the effective dose as presentedinICRPPublications60and103.Thecomputerprogramwasvalidatedagainst another ICRP dosimetry program, Dose and Risk Calculation (DCAL),thatemploysthesame computational framework in evaluation of occupational and environmental intakes of radionuclides. IDAC-Dose2.1 has a sub-module for absorbed dose calculations in spherical structures of different volumes and composition; this sub-module is intended for absorbed dose estimates in radiopharmaceutical therapy. For nine specific alpha emitters, the absorbed dose contribution from their decay products is also included in the committed absorbed dose calculations. Results: The absorbed doses and effective dose of 131I-iodide determined by IDAC-Dose2.1 were validated against the dosimetry program DCAL, showing identical results. IDAC-Dose2.1 was used to calculate absorbed doses for intravenously administered 18F-FDG and orally administered 99mTc-pertechnetate and 131I-iodide, three frequently used radiopharmaceuticals. Using the tissue weighting factors from ICRP Publication 103, the effective dose per administered activity was estimated to be 0.016 mSv/MBq for 18F-FDG, 0.014 mSv/MBq for 99mTc-pertechnetate, and 16 mSv/MBq for 131I-iodide. Conclusions: The internal dosimetry program IDAC-Dose2.1 was developed and applied to three radiopharmaceuticals for validation against DCAL and to generate improved absorbed dose estimations for diagnostic nuclear medicine using specific absorbed fraction values of the ICRP computational voxel phantoms. The sub-module for absorbed dose calculations in spherical structures 1 mm to 9 cm in diameter and different tissue composition was included to broaden the clinical usefulness of the program. The IDAC-Dose2.1 program is free software for research and available for download at http://www.idac-dose.org. Keywords: Internal dosimetry, ICRP, IDAC, DCAL, Effective dose, Radiopharmaceuticals, Diagnostic nuclear medicine * Correspondence: [email protected] 1Medical Radiation Physics, Department of Translational Medicine, Malmö, Lund University, Skåne University Hospital, SE-205 02 Malmö, Sweden Full list of author information is available at the end of the article © The Author(s). 2017 Open Access This article is distributed under the terms of the Creative Commons Attribution 4.0 International License (http://creativecommons.org/licenses/by/4.0/), which permits unrestricted use, distribution, and reproduction in any medium, provided you give appropriate credit to the original author(s) and the source, provide a link to the Creative Commons license, and indicate if changes were made. Andersson et al. EJNMMI Research (2017) 7:88 Page 2 of 10 Background radionuclide-specific neutron SAF values, are presented in In radiological protection, it is important to be able to ICRP Publication 133 [21]. perform valid calculations of the absorbed dose in The introduction of more realistic anatomical models organs and tissues of the body for persons exposed to with more detailed biokinetic models regarding the up- external radiation sources and radiation from internally take, distribution, and retention of radiopharmaceuticals distributed radionuclides. Computer programs are needed creates the possibility of more accurate and representative because it is difficult to measure the absorbed dose to absorbed dose estimations. One of the main challenges for organs and tissues. For radionuclides entering the body by medical internal radiation dosimetry is to select an appro- inhalation and ingestion in occupational and environmen- priate biokinetic model describing the uptake, retention, tal exposures, the Dose and Risk Calculation (DCAL) [1] and clearance of the radiopharmaceutical of interest. For program has been used to derive nuclide-specific dose internal absorbed dose calculations for the Reference coefficients published by the International Commission on Person, updating the general biokinetic models includes Radiological Protection (ICRP). In addition, “Internal Dose more realistic representations ofthealimentaryandrespira- Assessed by Computer” (IDAC-Dose) [2, 3] program has tory tract models. Updated nuclear decay data are also been used by ICRP to tabulate dose coefficients for patients available in ICRP Publication 107 [22], and performing undergoing examinations with radiopharmaceuticals in absorbed dose estimations based on the new, more realistic nuclear medicine (mainly intravenous administration, SAF values [21] will allow more detailed absorbed dose sometimes orally or via inhalation). Similar programs calculations and will provide more accurate absorbed dose have been developed by other groups (RADAR [4, 5], etc.). estimations for patients examined with radiopharmaceuti- The ICRP Task Group on “Radiation dose to patients in cals. The aim of this work was to update the IDAC-Dose2.0 diagnostic nuclear medicine” has issued several publica- [23] created to calculate absorbed dose based on earlier tions [6–9] on the absorbed dose to patients from different published SAF values [24] for the ICRP adult computational clinically used diagnostic radiopharmaceuticals using the voxel phantoms [20]. The updated version, IDAC-Dose2.1, IDAC-Dose1.0 program. DCAL has been used by the ICRP is based on the SAF values published by the ICRP [21] and Task Group on “Dose calculations” to estimate doses to implements the computational framework for internal dose occupationally exposed individuals and members of the assessment already used by ICRP for absorbed dose public [10–15]. At that time, the absorbed dose calcula- calculations at occupational and public exposures. If tions using DCAL and IDAC-Dose1.0 were based on the reliable biokinetic data for the substances are available, stylised family anatomical phantoms described by Cristy the program enables calculations of absorbed dose and and Eckerman [16] and based on the data given in ICRP effective dose up to 1252 radionuclides published in Publication 23 for the “Reference Man” [17]. The stylised ICRP Publication 107. This update allows users to perform phantoms were described by linear and quadratic equa- absorbed dose calculations based on biokinetic data gener- tions and included 24 specific organs. In IDAC-Dose1.0, ated in different research programs. radionuclide-specific absorbed dose calculations were in- A secondary aim of this work was to benchmark terpolated from monoenergetic photon-specific absorbed results obtained from IDAC-Dose2.1 with those obtained fractions (SAFs) between 10 and 4 MeV, and electrons using DCAL under the same reference conditions. Both were assumed to be locally absorbed. IDAC-Dose2.1 and the new version of DCAL base their An updated set of reference values for basic anatomical dose calculations on the same ICRP computational frame- and physiological data was given in ICRP Publication 89 work for internal dose assessment [21]. IDAC-Dose2.1 will [18] for both male and female subjects of six different ages be used by the ICRP Task Group on “Radiation dose to (newborn, 1, 5, 10, and 15 years, and adult) based on sta- patients in diagnostic nuclear medicine” for new absorbed tistics for Western Europeans and North Americans. In dose calculations for patients in future ICRP publications, developing guidelines to limit potential stochastic effects whereas the DCAL will be used by the ICRP Task Group (mainly based on cancer statistics) from radiation expos- on “internal dose coefficients” in their publications on ure (external and internal), the ICRP defines an idealised dose estimates for occupational and public intake of person called the “Reference Person” and the dosimetric radionuclides [25, 26]. quantity effective dose [19]. To calculate the effective dose, the equivalent doses to the “Reference Male” and Absorbed dose and effective dose “Reference Female” are averaged. The underlying anatom- MIRD pamphlet 21 [27] defines the mean absorbed dose ical and physiological reference values for the two refer- (D) to a target region (rT) for a time-independent system ence individuals are presented in ICRP Publication 89 [18]. as Eq. 1: Voxel phantoms describing these two adults are given in X ICRP Publication 110 [20], and SAF values for monoener- e DrðÞ¼T ; T D A ðÞrS; T D SrðÞT ←rS ½Gy ð1Þ getic photons, electrons, and alpha particles, as well as rS Andersson et al. EJNMMI Research (2017) 7:88 Page 3 of 10 where Ã(rS, TD) is the time-integrated or cumulated
Recommended publications
  • 1 RC-6 Internal Dosimetry the Science and Art of Internal Dose
    RC-6 Internal Dosimetry The science and art of internal dose assessment H. Doerfel a, A. Andrasi b, M. Bailey c, V. Berkovski d, E. Blanchardon e, C.-M. Castellani f, R. Cruz-Suarez g, G. Etherington c, C. Hurtgen h, B. LeGuen i, I. Malatova j, J. Marsh c, J. Stather c aIDEA System GmbH, Am Burgweg 4, 76227 Karlsruhe, Germany, [email protected] bKFKI Atomic Energy Research Institute, Budapest, Hungary cRadiation Protection Division, Health Protection Agency, Chilton, Didcot, UK dRadiation Protection Institute, Kiev, Ukraine eInstitut de Radioprotection et de Sûreté Nucleaire, Fontenay-aux-Roses, France fENEA Radiation Protection Institute, Bologna, Italia gInternational Atomic Energy Agency, Vienna, Austria hSCK•CEN Belgian Nuclear Research Centre, Mol, Belgium iElectricite de France, Saint-Denis, France jNRPI, Prague, Czech Republic 1 Abstract Doses from intakes of radionuclides cannot be measured but must be assessed from monitoring, such as whole body counting or urinary excretion measurements. Such assessments require application of a biokinetic model and estimation of the exposure time, material properties, etc. Because of the variety of parameters involved, the results of such assessments may vary over a wide range, according to the skill and the experience of the assessor. The refresher course gives an overview over the state of the art of the determination of internal dose. The first part of the course deals with the measuring techniques for individual incorporation monitoring i.e (i) direct measurement of activity in the whole body or organs, (ii) measurement of activity excreted with urine and faeces, and (iii) measurement of activity in the breathing zone or at the workplace, respectively.
    [Show full text]
  • Forschungszentrum Karlsruhe Third European Intercomparison Exercise
    Forschungszentrum Karlsruhe Technik und Umwelt Wissenschaftliche Berichte FZKA 6457 Third European Intercomparison Exercise on Internal Dose Assessment Results of a Research Programme in the Framework of the EULEP/EURADOS Action Group “Derivation of Parameter Values for Application to the New Model of the Human Respiratory Tract for Occupational Exposure” 1997-1999 H. Doerfel, A. Andrasi 1), M. R. Bailey 2), A. Birchall 2), C.-M. Castellani 3), C. Hurtgen 4), N. Jarvis 2), L. Johansson 5), B. LeGuen 6), G. Tarroni 3) Hauptabteilung Sicherheit 1) AERI, Budapest, Hungary 2) NRPB, Chilton Didcot, United Kingdom 3) ENEA, Bologna, Italy 4) CEN/SCK, Mol, Belgium 5) University of Umea, Umea, Sweden 6) EDF-GDF, Saint Denis Cedex, France Forschungszentrum Karlsruhe GmbH, Karlsruhe 2000 Abstract The EULEP/EURADOS Action Group „Derivation of Parameter Values for Application to the New Model of the Human Respiratory Tract for Occupational Exposure“ has initiated a new intercomparison exercise on internal dose assessment. During the last few years the ICRP has developed a new generation of more realistic internal dosimetry models, including the Human Respiratory Tract Model (ICRP Publication 66) and recycling systemic models for actinides. These models have been used to calculate dose coefficients, which have been adopted in the revised EURATOM Directive. This recent intercomparison exercise gave special consideration to the effects of the new models and the choice of input parameters on the assessment of internal doses from monitoring results. It also took into account some aspects which have not been considered in previous exercises, such as air monitoring, natural radionuclides, exposure of the public, artificially created cases and artificially reduced information.
    [Show full text]
  • Medical Management of Persons Internally Contaminated with Radionuclides in a Nuclear Or Radiological Emergency
    CONTAMINATION EPR-INTERNAL AND RESPONSE PREPAREDNESS EMERGENCY EPR-INTERNAL EPR-INTERNAL CONTAMINATION CONTAMINATION 2018 2018 2018 Medical Management of Persons Internally Contaminated with Radionuclides in a Nuclear or Radiological Emergency Contaminatedin aNuclear with Radionuclides Internally of Persons Management Medical Medical Management of Persons Internally Contaminated with Radionuclides in a Nuclear or Radiological Emergency A Manual for Medical Personnel Jointly sponsored by the Endorsed by AMERICAN SOCIETY FOR RADIATION ONCOLOGY INTERNATIONAL ATOMIC ENERGY AGENCY V I E N N A ISSN 2518–685X @ IAEA SAFETY STANDARDS AND RELATED PUBLICATIONS IAEA SAFETY STANDARDS Under the terms of Article III of its Statute, the IAEA is authorized to establish or adopt standards of safety for protection of health and minimization of danger to life and property, and to provide for the application of these standards. The publications by means of which the IAEA establishes standards are issued in the IAEA Safety Standards Series. This series covers nuclear safety, radiation safety, transport safety and waste safety. The publication categories in the series are Safety Fundamentals, Safety Requirements and Safety Guides. Information on the IAEA’s safety standards programme is available on the IAEA Internet site http://www-ns.iaea.org/standards/ The site provides the texts in English of published and draft safety standards. The texts of safety standards issued in Arabic, Chinese, French, Russian and Spanish, the IAEA Safety Glossary and a status report for safety standards under development are also available. For further information, please contact the IAEA at: Vienna International Centre, PO Box 100, 1400 Vienna, Austria. All users of IAEA safety standards are invited to inform the IAEA of experience in their use (e.g.
    [Show full text]
  • Radiation Quantities and Units Definitions
    Radiation Quantities and Units Definitions The quantities and units of radiation dose are inherently more complex than those used in toxicology or pharmacology, and additional complexity has resulted from several changes required by evolving concepts in radiation dosimetry. The first widely used physical quantity of radiation was “exposure,” related to the ability of x or gamma radiation to ionize air; its unit was the roentgen (R). Exposure was limited to photon radiation with energy less than 2.5 MeV. The quantity “absorbed dose” (D) was introduced because it was applicable to all forms of ionizing radiation and absorbing materials. Absorbed dose is energy deposited per unit mass, and its original unit was the rep (roentgen equivalent-physical); 1 rep equaled 93 ergs per g (0.0093 J per kg) of absorbing material. The rep was replaced with the rad (radiation absorbed dose); 1 rad equaled 100 ergs per g (0.01 J per kg). The “dose equivalent” (H) and its unit, the rem (roentgen equivalent-man), were introduced to account for the different biologic effects of the same absorbed dose from different types of radiation; H is the product of D, Q, and N at a point of interest in tissue, where D is absorbed dose, Q is the quality factor, and N is the product of any other modifying factors. The “effective dose equivalent” was introduced to include the different sensitivities of individual tissues and organs, which are important for internal dosimetry: its unit is the same as the unit of “dose equivalent.” In the 1990 recommendations of the International Commission on Radiological Protection (ICRP 1991), the use of N was dropped and the radiation weighting factor (WR) was substituted for Q.
    [Show full text]
  • Perspective on Internal Contamination and Dose
    Perspective on Internal Contamination and Dose Hanford Internal Dosimetry Program 1 What is meant by contamination and dose? Contamination: the unwanted presence of radioactive material. Dose: energy deposited in the body by radioactive decay of contamination 2 External and Internal Sources External exposure: Route of intake: Route of intake: no intake inhalation skin absorption Route of intake: Route of intake: wound exposure ingestion 3 Measuring External Dose Dosimeters measure dose from external sources. Left: Hanford Left: Hanford combination standard neutron dosimeter dosimeter Below: Hanford extremity dosimeter Dose from internal contamination (within the body) cannot be measured by dosimeters. 4 External Dose vs. Internal Dose External Dose Internal Dose • Generally, easy to measure with • Requires determination from a dosimeter bioassay measurements of • Usually reported as a “whole material in the body or excreted body” or “effective” dose from the body • Type of bioassay depends on radioactive material • Optimum type of bioassay depends on radioactive material and time since intake occurred 5 Bioassay Methods There are several bioassay methods used to determine intake and internal dose: • Whole body exam/count Left: a whole body • Chest count count and lung count being taken • Wound count • Urine/fecal sample analysis Left: the in-home kit for collecting urine or fecal samples for bioassay 6 How Critical is Time to Bioassay? Don’t sample too soon… but don’t wait too long • The material may not be present in the bladder or bowel if the sample is taken too soon. • Dose detection capability varies with time after intake. Getting a bioassay at the right time can provide a more accurate analysis.
    [Show full text]
  • External and Internal Dosimetry
    Chapter 7 External and Internal Dosimetry H-117 – Introductory Health Physics Slide 1 Objectives ¾ Discuss factors influencing external and internal doses ¾ Define terms used in external dosimetry ¾ Discuss external dosimeters such as TLDs, film badges, OSL dosimeters, pocket chambers, and electronic dosimetry H-117 – Introductory Health Physics Slide 2 Objectives ¾ Define terms used in internal dosimetry ¾ Discuss dose units and limits ¾ Define the ALI, DAC and DAC-hr ¾ Discuss radiation signs and postings H-117 – Introductory Health Physics Slide 3 Objectives ¾ Discuss types of bioassays ¾ Describe internal dose measuring equipment and facilities ¾ Discuss principles of internal dose calculation and work sample problems H-117 – Introductory Health Physics Slide 4 External Dosimetry H-117 – Introductory Health Physics Slide 5 External Dosimetry Gamma, beta or neutron radiation emitted by radioactive material outside the body irradiates the skin, lens of the eye, extremities & the whole body (i.e. internal organs) H-117 – Introductory Health Physics Slide 6 External Dosimetry (cont.) ¾ Alpha particles cannot penetrate the dead layer of skin (0.007 cm) ¾ Beta particles are primarily a skin hazard. However, energetic betas can penetrate the lens of an eye (0.3 cm) and deeper tissue (1 cm) ¾ Beta sources can produce more penetrating radiation through bremsstrahlung ¾ Primary sources of external exposure are photons and neutrons ¾ External dose must be measured by means of appropriate dosimeters H-117 – Introductory Health Physics Slide 7
    [Show full text]
  • Internal Dosimetry Co-Exposure Data for the Savannah River Site
    Page 1 of 287 DOE Review Release 09/04/2020 ORAUT-OTIB-0081 Rev. 05 Internal Dosimetry Co-Exposure Data for the Effective Date: 09/01/2020 Savannah River Site Supersedes: Revision 04 Subject Expert(s): Matthew G. Arno, James M. Mahathy, and Nancy Chalmers Document Owner Signature on File Approval Date: 08/24/2020 Approval: Matthew G. Arno, Document Owner Concurrence: Signature on File Concurrence Date: 08/24/2020 John M. Byrne, Objective 1 Manager Concurrence: Signature on File Concurrence Date: 08/24/2020 Scott R. Siebert, Objective 3 Manager Concurrence: Vickie S. Short Signature on File for Concurrence Date: 08/24/2020 Kate Kimpan, Project Director Approval: Signature on File Approval Date: 08/25/2020 Timothy D. Taulbee, Associate Director for Science FOR DOCUMENTS MARKED AS A TOTAL REWRITE, REVISION, OR PAGE CHANGE, REPLACE THE PRIOR REVISION AND DISCARD / DESTROY ALL COPIES OF THE PRIOR REVISION. New Total Rewrite Revision Page Change Document No. ORAUT-OTIB-0081 Revision No. 05 Effective Date: 09/01/2020 Page 2 of 287 PUBLICATION RECORD EFFECTIVE REVISION DATE NUMBER DESCRIPTION 02/08/2013 00 New technical information bulletin to provide internal coworker data for the Savannah River Site. Incorporates formal internal and NIOSH review comments. Training required: As determined by the Objective Manager. Initiated by Matthew Arno. 04/01/2013 01 Revision initiated to correct the values provided in Tables 5-6, Type S uranium intake rates for 1968 through 2007, 5-10, changed end date from 2006 to 2007, A-3, plutonium bioassay data for 1955 through 2007, and A-8, neptunium bioassay data for 1991 through 2007.
    [Show full text]
  • Internal Dosimetry Hazard and Risk Assessments: Methods and Applications G
    DOSIMETRY AND INSTRUMENTATION INTERNAL DOSIMETRY HAZARD AND RISK ASSESSMENTS: METHODS AND APPLICATIONS G. A. Roberts RWE NUKEM Limited, Didcot, UK ABSTRACT Routine internal dose exposures are typically (in the UK nuclear industry) less than external dose exposures: however, the costs of internal dosimetry monitoring programmes can be significantly greater than those for external dosimetry. For this reason decisions on when to apply routine monitoring programmes, and the nature of these programmes, can be more critical than for external dosimetry programmes. This paper describes various methods for performing hazard and risk assessments which are being developed by RWE NUKEM Limited Approved Dosimetry Services to provide an indication when routine internal dosimetry monitoring should be considered. INTRODUCTION The estimation of internal dose needs to be inferred from the measurement of activity in the individual (by in-vivo or in-vitro methods) or in the workplace environment. A variety of monitoring methods are available for making these measurements [1]. A review of the current monitoring practices within European Union countries was included within the OMINEX project (Optimisation of Monitoring for Internal Exposure) [2] and are summarised in Table 1. Type of Total Monitoring method Monitoring operation number In vivo Bioassay SAS/PAS Routine Special Both Nuclear power 34 33 15 7 8 4 27 plant Reprocessing 2 2 2 - - - 1 Fuel 7 6 6 2 3 2 5 fabrication Decommiss- 6 5 6 1 2 2 5 ioning Research 19 17 12 5 3 5 16 Non-nuclear 3 3 3 2 2 2 2 SAS – static air sampling PAS – personal air sampling Table 1: Number of organisations using each monitoring method for routine or special monitoring, classified by type of operation.
    [Show full text]
  • INTERNAL DOSIMETRY for NUCLEAR POWER PROGRAM (Dosimeter Dalaman Untuk Program Kuasa Nuklear)
    Konvensyen Teknikal Nuklear Malaysia 13 – 15 Sep 2011 INTERNAL DOSIMETRY FOR NUCLEAR POWER PROGRAM (Dosimeter dalaman untuk Program Kuasa Nuklear) Yii Mei-Wo Waste and Environmental Technology Division Malaysian Nuclear Agency Bangi, 43000 Kajang, Malaysia Tel: 03-8925 0510 Fax: 03-8928 2977 E-mail: [email protected] Abstract Internal dosimetry which refers to dosage estimation from internal part of an individual body is an important and compulsory component in order to ensure the safety of the personnel involved in operational of a Nuclear Power Program. Radionuclides particle may deposit in the human being through several pathways and release wave and/or particle radiation to irradiate that person and give dose to body until it been excreted or completely decayed from the body. Type of radionuclides of concerning, monitoring program, equipments and technique used to measure the concentration level of such radionuclides and dose calculation will be discussed in this article along with the role and capability of Malaysian Nuclear Agency. Abstrak Dosimetri dalaman yang merujuk kepada penganggran dos dari bahagian dalaman badan seseorang individu adalah satu komponen mustahak dan wajib untuk menjamin keselamatan personel yang terlibat dalam pengendalian Program Kuasa Nuklear. Patikel radionuklid boleh memasuki ke dalam manusia melalui beberapa laluan dan membebaskan sinaran gelombang dan/atau zarah untuk mengiridiasi manusia dan memberi dos kepada badan sehingga ia disingkirkan atau menyepai habis dari badan manusia. Jenis radionuklid yang berkenaan, program pemantauan, peralatan dan teknik pengukuran tahap kepekatan radionuklid tersebut serta pengiraan dos akan dibincang dalam artikel ini bersama peranan dan kemampuan Agensi Nuklear Malaysia. Keyword: dose; internal dosimetry; Nuclear Power Program; monitoring; INTRODUCTION When a personnel is dealing with ionizing radiation, he may be exposed to the radiation either external or internally.
    [Show full text]
  • Dosimetry Issuance Request Form
    Dosimeter Issuance and Information Request Form Instructions: Complete and submit this form if you will work under an RUA that requires external or internal radiation monitoring (see checkboxes under “Precautions Required” on the RUA form). Last Name:________________________________ , First Name:______________________________ __ CalNet ID:_________________________ ________, Birthdate (Month/Day/Year):____________________ __ Gender: Male Female [ ] I am a declared pregnant worker and will will work under an RUA or { will not be working with radiation under a specific RUA at this time. I am being added to RUA ___________________which has a requirement for: External monitoring (TLD ring, body badge or neutron badge) [ ] Bioassay (thyroid scan or urinalysis) [ ] RUA requires: RUA requires: TLD ring [ ] Body Badge [ ] Neutron Badge [ ] Thyroid Scan [ ] Urinalysis [ ] Other analysis per listed under “Precautions” [ ] Previous radiation monitoring (radiation badges and/or bioassays): Yes [ ] No [ ]: Within the current calendar year I have been monitored for external radiation exposure and/or internal radiation uptake. I give authorization for these records to be released to the University of California, Berkeley EH&S. Your ID no. at organization: ____________________________ Street address:________________________________________ Approx. dates of rad monitoring:__________________________ City, state & zip:_______________________________________ Organization name____________________________________ ATTN:_______________________________________________ [ ] I had radiation monitoring from more than one organization this year, please see attached sheet with added information. [ ] I have been informed that additional information regarding radiation exposure during pregnancy is available from the EH&S Radiation Safety website. [ ] I have been informed of the frequency for bioassays and/or the exchange of external dosimeters and agree to participate in bioassays and/or to have my assigned dosimeter available for exchange at the designated frequency.
    [Show full text]
  • Comparison of Different Internal Dosimetry Systems for Selected Radionuclides Important to Nuclear Power Production
    ORNL/TM-2013/226 Comparison of Different Internal Dosimetry Systems for Selected Radionuclides Important to Nuclear Power Production June 2013 R. W. Leggett K. F. Eckerman R. P. Manger Oak Ridge National Laboratory Oak Ridge, Tennessee 37831 Prepared for the U.S. Nuclear Regulatory Commission Office of Nuclear Regulatory Research CONTENTS LIST OF TABLES ...................................................................................................................... v LIST OF FIGURES ................................................................................................................ viii EXECUTIVE SUMMARY ........................................................................................................ 1 Background ............................................................................................................................ 1 Objectives of this report ......................................................................................................... 1 Method of dose comparison ................................................................................................... 2 Main results ............................................................................................................................ 3 Differences in fundamental dosimetric concepts of NRC77 and later systems ................ 3 Comparison of dose estimates for individual radionuclides in drinking water ................. 4 Comparison of dose estimates for inhalation of individual radionuclides .......................
    [Show full text]
  • Report of CM Internal Dosimetry
    INTERNATIONAL ATOMIC ENERGY AGENCY Report of a Consultancy Meeting held 26-28 September 2011 at the IAEA Headquarters in Vienna FOREWORD The Dosimetry and Medical Radiation Physics (DMRP) section’s efforts in Nuclear Medicine Physics follow the section’s overall focus on Quality Assurance in radiation medicine, with special emphasis on educating and training medical physicists. For nuclear medicine physics, extra effort has previously been placed on proper radioactivity measurements. Currently the section is involved in providing guidelines for proper quantification of nuclear medicine images. These efforts set the stage for patient-specific dosimetry, a requirement for therapeutic nuclear medicine but also useful for diagnostic procedures. A consultants’ meeting was arranged to provide advice to the Agency on the current status of the field, as well as identifying any gaps that should be addressed. The specific purpose of the meeting was to review current guidelines for internal dosimetry in nuclear medicine, and to provide recommendations for international harmonization of this field. The consultants were Dr. Manuel Bardies, Centre de Recherche en Cancérologie de Toulouse, France; Dr. Michael Lassmann, University of Würzburg, Germany; Dr. Wesley Bolch, University of Florida, USA; and Dr. George Sgouros, Johns Hopkins University, USA. Scientific secretary for the meeting was Stig Palm, DMRP/NAHU. CONTENTS 1. ROLE OF INTERNAL DOSIMETRY IN NUCLEAR MEDICINE ............................... 1 1.1. Diagnostic Nuclear Medicine ............................................................................
    [Show full text]