Radiation Dose in Radiotherapy from Prescription Deliveryto
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Personal Radiation Monitoring
Personal Radiation Monitoring Tim Finney 2020 Radiation monitoring Curtin staff and students who work with x-ray machines, neutron generators, or radioactive substances are monitored for exposure to ionising radiation. The objective of radiation monitoring is to ensure that existing safety procedures keep radiation exposure As Low As Reasonably Achievable (ALARA). Personal radiation monitoring badges Radiation exposure is measured using personal radiation monitoring badges. Badges contain a substance that registers how much radiation has been received. Here is the process by which a user’s radiation dose is measured: 1. The user is given a badge to wear 2. The user wears the badge for a set time period (usually three months) 3. At the end of the set time, the user returns the badge 4. The badge is sent away to be read 5. A dose report is issued. These steps are repeated until monitoring is no longer required. Badges are supplied by a personal radiation monitoring service provider. Curtin uses a service provider named Landauer. In addition to user badges, the service provider sends control badges that are kept on site in a safe place away from radiation sources. The service provider reads each badge using a process that extracts a signal from the substance contained in the badge to obtain a dose measurement. (Optically stimulated luminescence is one such process.) The dose received by the control badge is subtracted from the user badge reading to obtain the user dose during the monitoring period. Version 1.0 Uncontrolled document when printed Health and Safety Page 1 of 7 A personal radiation monitoring badge Important Radiation monitoring badges do not protect you from radiation exposure. -
Potential Efficacy of the Monte Carlo Dose Calculations of 6MV Flattening
Potential Efficacy of the Monte Carlo Dose Calculations of 6MV Flattening Filter-Free Photon Beam of M6™ Cyberknife® System by Taindra Neupane A Thesis Submitted to the Faculty of The Charles E. Schmidt College of Science in Partial Fulfillment of the Requirements for the Degree of Professional Science Master Florida Atlantic University Boca Raton, FL December 2018 Copyright 2018 by Taindra Neupane ii Acknowledgements First, I would like to express my gratitude to my Advisor, Dr. Charles Shang for providing me the opportuinity to do this research at Lynn Cancer Institute, Boca Raton Regional Hospital at Boca Raton and his guidance, enthusiasm and motivation which helped me to accomplish this reasearch. I would also like to thank my committee members, Dr. Theodora Leventouri, and Dr. Silvia Pella for their constructive guidance and support. I am particularly grateful to Dr. Theodora Leventouri, Professor of Physics, for her relentless encouragement, direction and assistance for my academics at the department. I am also thankful to all the faculty members and fellow graduate students in the department of physics who contributed to my learning process directly and indirectly. Finally, I would like to thank Dr. Francescon and Dr. Reynaert for providing the sample input files, the EGSnrc Google Plus Forum for answering my questions during the MC simulations, Musfiqur Rahaman for his help in technical problems, and my family members for their continuous support. iv Abstract Author: Taindra Neupane Title: Potential Efficacy of the Monte Carlo Dose Calculations of 6MV Flattening Filter-Free Photon Beam of M6™ Cyberknife® System Institution: Florida Atlantic University Thesis Co-Advisors: Dr. -
Proper Use of Radiation Dose Metric Tracking for Patients Undergoing Medical Imaging Exams
Proper Use of Radiation Dose Metric Tracking for Patients Undergoing Medical Imaging Exams Frequently Asked Questions Introduction In August of 2021, the American Association of Physicists in Medicine (AAPM), the American College of Radiology (ACR), and the Health Physics Society (HPS) jointly released the following position statement advising against using information about a patient’s previous cumulative dose information from medical imaging exams to decide the appropriateness of future imaging exams. This statement was also endorsed by the Radiological Society of North America (RSNA). It is the position of the American Association of Physicists in Medicine (AAPM), the American College of Radiology (ACR), and the Health Physics Society (HPS) that the decision to perform a medical imaging exam should be based on clinical grounds, including the information available from prior imaging results, and not on the dose from prior imaging-related radiation exposures. AAPM has long advised, as recommended by the International Commission on Radiological Protection (ICRP), that justification of potential patient benefit and subsequent optimization of medical imaging exposures are the most appropriate actions to take to protect patients from unnecessary medical exposures. This is consistent with the foundational principles of radiation protection in medicine, namely that patient radiation dose limits are inappropriate for medical imaging exposures. Therefore, the AAPM recommends against using dose values, including effective dose, from a patient’s prior imaging exams for the purposes of medical decision making. Using quantities such as cumulative effective dose may, unintentionally or by institutional or regulatory policy, negatively impact medical decisions and patient care. This position statement applies to the use of metrics to longitudinally track a patient’s dose from medical radiation exposures and infer potential stochastic risk from them. -
Automation of the Monte Carlo Simulation of Medical Linear
doctoral dissertation AUTOMATIONOFTHEMONTECARLOSIMULATIONOF MEDICALLINEARACCELERATORS miguel lázaro rodríguez castillo Institut de Tecniques` Energètiques Universitat Politècnica de Catalunya Barcelona - November 20th, 2015 Co-supervisors: Priv.-Doz. Dr. Lorenzo Brualla Klinik- und Poliklinik für Strahlentherapie Universitätsklinikum Essen Universität Duisburg-Essen Dr. Josep Sempau Institut de Tecniques` Energètiques Universitat Politècnica de Catalunya Para mis padres, mi esposa y mis hijos The enjoyment of one’s tools is an essential ingredient of successful work — Donald E. Knuth PUBLICATIONS Publications in scientific journals related to this thesis: • M. Rodriguez, J. Sempau, A. Fogliata, L. Cozzi, W. Sauerwein, and L. Brualla. A geometrical model for the Monte Carlo simu- lation of the TrueBeam linac. Phys. Med. Biol., 60:N219–N229, 2015. • M. Rodriguez, J. Sempau, and L. Brualla. Study of the electron transport parameters used in penelope for the Monte Carlo simulation of linac targets. Med. Phys., 42:2877–2881, 2015. • M. F. Belosi, M. Rodriguez, A. Fogliata, L. Cozzi, J. Sempau, A. Clivio, G. Nicolini, E. Vanetti, H. Krauss, C. Khamphan, P. Fe- noglietto, J. Puxeu, D. Fedele, P. Mancosu, and L. Brualla. Monte Carlo simulation of TrueBeam flattening-filter-free beams using Varian phase-space files: Comparison with experimental data. Med. Phys., 41:051707, 2014. • M. Rodriguez, J. Sempau, and L. Brualla. PRIMO: A graphi- cal environment for the Monte Carlo simulation of Varian and Elekta linacs. Strahlenther. Onkol., 189:881–886, 2013. • M. Rodriguez, J. Sempau, and L. Brualla. A combined approach of variance-reduction techniques for the efficient Monte Carlo simulation of linacs. Phys. Med. Biol., 57:3013–3024, 2012. Additional publication in a scientific journal related to this thesis: • M. -
Cumulative Radiation Dose in Patients Admitted with Subarachnoid Hemorrhage: a Prospective PATIENT SAFETY Study Using a Self-Developing Film Badge
Cumulative Radiation Dose in Patients Admitted with Subarachnoid Hemorrhage: A Prospective PATIENT SAFETY Study Using a Self-Developing Film Badge A.C. Mamourian BACKGROUND AND PURPOSE: While considerable attention has been directed to reducing the x-ray H. Young dose of individual imaging studies, there is little information available on the cumulative dose during imaging-intensive hospitalizations. We used a radiation-sensitive badge on 12 patients admitted with M.F. Stiefel SAH to determine if this approach was feasible and to measure the extent of their x-ray exposure. MATERIALS AND METHODS: After obtaining informed consent, we assigned a badge to each of 12 patients and used it for all brain imaging studies during their ICU stay. Cumulative dose was deter- mined by quantifying exposure on the badge and correlating it with the number and type of examinations. RESULTS: The average skin dose for the 3 patients who had only diagnostic DSA without endovascular intervention was 0.4 Gy (0.2–0.6 Gy). The average skin dose of the 8 patients who had both diagnostic DSA and interventions (eg, intra-arterial treatment of vasospasm and coiling of aneurysms) was 0.9 Gy (1.8–0.4 Gy). One patient had only CT examinations. There was no effort made to include or exclude the badge in the working view during interventions. CONCLUSIONS: It is feasible to incorporate a film badge that uses a visual scale to monitor the x-ray dose into the care of hospitalized patients. Cumulative skin doses in excess of 1 Gy were not uncommon (3/12) in this group of patients with acute SAH. -
Dose Calculation Algorithms for External Radiation Therapy: an Overview for Practitioners
applied sciences Review Dose Calculation Algorithms for External Radiation Therapy: An Overview for Practitioners Fortuna De Martino 1, Stefania Clemente 2, Christian Graeff 3, Giuseppe Palma 4,*,† and Laura Cella 4,*,† 1 Post Graduate School in Medical Physics, University of Naples Federico II, 80131 Naples, Italy; [email protected] 2 Unit of Medical Physics and Radioprotection, A.O.U Policlinico Federico II, 80131 Naples, Italy; [email protected] 3 Biophysics Department, GSI Helmholtzzentrum für Schwerionenforschung, 64291 Darmstadt, Germany; [email protected] 4 Institute of Biostructure and Bioimaging, National Research Council (CNR), 80145 Naples, Italy * Correspondence: [email protected] (G.P.); [email protected] (L.C.) † These authors share senior authorship. Featured Application: Radiation therapy treatment planning. Abstract: Radiation therapy (RT) is a constantly evolving therapeutic technique; improvements are continuously being introduced for both methodological and practical aspects. Among the features that have undergone a huge evolution in recent decades, dose calculation algorithms are still rapidly changing. This process is propelled by the awareness that the agreement between the delivered and calculated doses is of paramount relevance in RT, since it could largely affect clinical outcomes. The Citation: De Martino, F.; Clemente, aim of this work is to provide an overall picture of the main dose calculation algorithms currently S.; Graeff, C.; Palma, G.; Cella, L. used in RT, summarizing their underlying physical models and mathematical bases, and highlighting Dose Calculation Algorithms for their strengths and weaknesses, referring to the most recent studies on algorithm comparisons. External Radiation Therapy: An This handy guide is meant to provide a clear and concise overview of the topic, which will prove Overview for Practitioners. -
Proton Beam Radiotherapy
DESIGN AND SIMULATION OF A PASSIVE-SCATTERING NOZZLE IN PROTON BEAM RADIOTHERAPY A Thesis by FADA GUAN Submitted to the Office of Graduate Studies of Texas A&M University in partial fulfillment of the requirements for the degree of MASTER OF SCIENCE December 2009 Major Subject: Health Physics DESIGN AND SIMULATION OF A PASSIVE-SCATTERING NOZZLE IN PROTON BEAM RADIOTHERAPY A Thesis by FADA GUAN Submitted to the Office of Graduate Studies of Texas A&M University in partial fulfillment of the requirements for the degree of MASTER OF SCIENCE Approved by: Chair of Committee, John W. Poston, Sr. Committee Members, Leslie A. Braby Michael A. Walker Head of Department, Raymond J. Juzaitis December 2009 Major Subject: Health Physics iii ABSTRACT Design and Simulation of a Passive-Scattering Nozzle in Proton Beam Radiotherapy. (December 2009) Fada Guan, B.E., Tsinghua University, China Chair of Advisory Committee: Dr. John W. Poston, Sr. Proton beam radiotherapy is an emerging treatment tool for cancer. Its basic principle is to use a high-energy proton beam to deposit energy in a tumor to kill the cancer cells while sparing the surrounding healthy tissues. The therapeutic proton beam can be either a broad beam or a narrow beam. In this research, we mainly focused on the design and simulation of the broad beam produced by a passive double-scattering system in a treatment nozzle. The NEU codes package is a specialized design tool for a passive double- scattering system in proton beam radiotherapy. MCNPX is a general-purpose Monte Carlo radiation transport code. In this research, we used the NEU codes package to design a passive double-scattering system, and we used MCNPX to simulate the transport of protons in the nozzle and a water phantom. -
Radiation Glossary
Radiation Glossary Activity The rate of disintegration (transformation) or decay of radioactive material. The units of activity are Curie (Ci) and the Becquerel (Bq). Agreement State Any state with which the U.S. Nuclear Regulatory Commission has entered into an effective agreement under subsection 274b. of the Atomic Energy Act of 1954, as amended. Under the agreement, the state regulates the use of by-product, source, and small quantities of special nuclear material within said state. Airborne Radioactive Material Radioactive material dispersed in the air in the form of dusts, fumes, particulates, mists, vapors, or gases. ALARA Acronym for "As Low As Reasonably Achievable". Making every reasonable effort to maintain exposures to ionizing radiation as far below the dose limits as practical, consistent with the purpose for which the licensed activity is undertaken. It takes into account the state of technology, the economics of improvements in relation to state of technology, the economics of improvements in relation to benefits to the public health and safety, societal and socioeconomic considerations, and in relation to utilization of radioactive materials and licensed materials in the public interest. Alpha Particle A positively charged particle ejected spontaneously from the nuclei of some radioactive elements. It is identical to a helium nucleus, with a mass number of 4 and a charge of +2. Annual Limit on Intake (ALI) Annual intake of a given radionuclide by "Reference Man" which would result in either a committed effective dose equivalent of 5 rems or a committed dose equivalent of 50 rems to an organ or tissue. Attenuation The process by which radiation is reduced in intensity when passing through some material. -
``Low Dose``And/Or``High Dose``In Radiation Protection: a Need To
IAEA-CN-67/154 "LOW DOSE" AND/OR "HIGH DOSE" IN RADIATION PROTECTION: A NEED TO SETTING CRITERIA FOR DOSE CLASSIFICATION Mehdi Sohrabi National Radiation Protection Department & XA9745670 Center for Research on Elevated Natural Radiation Atomic Energy Organization of Iran, Tehran ABSTRACT The "low dose" and/or "high dose" of ionizing radiation are common terms widely used in radiation applications, radiation protection and radiobiology, and natural radiation environment. Reading the title, the papers of this interesting and highly important conference and the related literature, one can simply raise the question; "What are the levels and/or criteria for defining a low dose or a high dose of ionizing radiation?". This is due to the fact that the criteria for these terms and for dose levels between these two extreme quantities have not yet been set, so that the terms relatively lower doses or higher doses are usually applied. Therefore, setting criteria for classification of radiation doses in the above mentioned areas seems a vital need. The author while realizing the existing problems to achieve this important task, has made efforts in this paper to justify this need and has proposed some criteria, in particular for the classification of natural radiation areas, based on a system of dose limitation. In radiation applications, a "low dose" is commonly associated to applications delivering a dose such as given to a patient in a medical diagnosis and a "high dose" is referred to a dose in applications such as radiotherapy, mutation breeding, control of sprouting, control of insects, delay ripening, and sterilization having a range of doses from 1 to 105 Gy, for which the term "high dose dosimetry" is applied [1]. -
Internal and External Exposure Exposure Routes 2.1
Exposure Routes Internal and External Exposure Exposure Routes 2.1 External exposure Internal exposure Body surface From outer space contamination and the sun Inhalation Suspended matters Food and drink consumption From a radiation Lungs generator Radio‐ pharmaceuticals Wound Buildings Ground Radiation coming from outside the body Radiation emitted within the body Radioactive The body is equally exposed to radiation in both cases. materials "Radiation exposure" refers to the situation where the body is in the presence of radiation. There are two types of radiation exposure, "internal exposure" and "external exposure." External exposure means to receive radiation that comes from radioactive materials existing on the ground, suspended in the air, or attached to clothes or the surface of the body (p.25 of Vol. 1, "External Exposure and Skin"). Conversely, internal exposure is caused (i) when a person has a meal and takes in radioactive materials in the food or drink (ingestion); (ii) when a person breathes in radioactive materials in the air (inhalation); (iii) when radioactive materials are absorbed through the skin (percutaneous absorption); (iv) when radioactive materials enter the body from a wound (wound contamination); and (v) when radiopharmaceuticals containing radioactive materials are administered for the purpose of medical treatment. Once radioactive materials enter the body, the body will continue to be exposed to radiation until the radioactive materials are excreted in the urine or feces (biological half-life) or as the radioactivity weakens over time (p.26 of Vol. 1, "Internal Exposure"). The difference between internal exposure and external exposure lies in whether the source that emits radiation is inside or outside the body. -
Radiation Safety
Ionizing Radiation Exposure from Radiologic Imaging Background The current and common unit of measurement of “absorbed” ionizing radiation is a milliSievert (mSv). Chest, abdomen or The increased use of diagnostic imaging requiring the use of pelvis CTs will typically expose one to between 6 – 8 mSv. “ionizing radiation,” the rapidly expanding use of computed tomography in the emergency setting, the introduction Specifically, a CT coronary angiogram may carry an of multi-detector CT units and newly reported concerns overall effective radiation dose in a 20 mSv range; the related to the human consequences of low-level radiation organ equivalent dose is quite different.7 Anthromorphic exposure have revitalized a long-standing concern over the mathematical phantoms have shown that such studies quantification and management of an individual’ s cumulative will expose 20-year-old female breast tissue to an organ 1,2,3 “medical” radiation exposure. Studies have shown that equivalent dose of 75 – 80 mSv, and lung tissue as high as 90 many physicians, including radiologists, have developed a mSv. The cancer incidence for a 20-year-old in this example is misconception that the shorter imaging acquisition times believed to be in the one in 143 range…quite significant! With have resulted in lower doses of radiation, when in fact many improvements in technology and CCTA imaging protocols, times the opposite is true. The multi-detector CT units today, effective dose has been reduced significantly, to less than 10 even with shorter scan times, expose patients to higher doses mSv in many cases. of radiation per scan than earlier units. -
Cumulative Radiation Exposure and Your Patient
Imaging Guideline JANUAry 2013 Cumulative Radiation Exposure and Your Patient This document, developed by Intermountain Healthcare’s Cardiovascular Clinical Program and Imaging Clinical Service, provides information on the cumulative radiation exposure reported in HELP2: the limitations of this information, why Intermountain is measuring and reporting it, tips on interpreting this information, and factors to consider when choosing an imaging procedure. Information in this document (click each item below to skip to that section): Please note that while this 1 What’s included — and not included — in your patient’s document provides evidence- cumulative radiation exposure as reported in HELP2 based information to consider in making treatment 2 Why Intermountain is measuring and reporting cumulative decisions for most patients, radiation exposure your approach should be adapted to meet the needs 3 The risks of radiation exposure of individual patients and 4 Factors to consider when choosing an imaging test situations, and should not 5 Discussing this information with your patient replace clinical judgment. 6 Estimated radiation exposures and lifetime risks from common procedures — a quick reference with resources A brief overview of this 1 WHAT’S INCLUDED IN MY PATIENT’S REPORTED topic is also available. For basic, concise information CUMULATIVE RADIATION EXPOSURE? on radiation exposure and The number reported for each patient: risk, see the brief Physician’s Guide to Radiation Exposure. • Includes four types of relatively higher-dose procedures: CT studies, angiography, nuclear cardiology, and cardiac catheterization procedures. • Begins in mid-2012: Earlier exposures are not included. • Does NOT include: Procedures performed at non-Intermountain facilities, other procedures besides the four listed above, or radiation (oncology) treatments.