Radiation Instrumentation
Total Page:16
File Type:pdf, Size:1020Kb
Load more
Recommended publications
-
Nuclear Threat
MANAGEMENT OF RADIOLOGIC CASUALTIES Nuclear Threat . Formerly .Soviet Union .Nuclear fallout . Now .NBC threat against civilians .Accidental exposure of workers and public Images: CIA, FBI Accidental Exposure in Brazil . Cesium-137 source found by scavengers in 1987 . Source broken open, contents shared . 112,800 surveyed for contamination . 120 externally contaminated only . 129 internally & externally contaminated . 20 required hospital treatment . 14 developed bone marrow depression . 8 treated with Granulocyte Macrophage Colony-Stimulating Factors (GM-CSF) . 4 died acute phase, hemorrhage, infection . 1 died in 1994 from liver failure Images: CIA Medical Staff Exposure Medical staff received doses: . Maximum 500 millirem (5 millisieverts) .Natural background radiation dose ~ 200 millirems annually . Average 20 millirem (0.2 millisieverts) .Equivalent to one chest X-ray Juarez, Mexico Incident . 400 curies of cobalt-60 in stainless steel therapy device sold for scrap . Ended up in recycled steel rebar . Wrong turn into Los Alamos lab . I0 people significantly exposed . 1 construction worker died .bone cancer . 109 houses demolished in Mexico Images: CIA US Experience 1944-1999 . 243 radiation accidents leading to “serious” classification . 790 people received significant exposure resulting in 30 fatalities .Incidents included: . 137 industrial . 80 medical . 11 criticality Image: DOE The Basics of Radiation Radiation is energy that comes from a source and travels through matter or space Radioactivity is the spontaneous emission of radiation: . Either directly from unstable atomic nuclei, or . As a consequence of a nuclear reaction, or . Machine – produced (X-ray) Image: NOAA Contamination . Defined as internal or external deposition of radioactive particles . Irradiation continues until source removed by washing, flushing or radioactive decay . -
The Utilization of MOSFET Dosimeters for Clinical Measurements in Radiology
The Utilization of MOSFET Dosimeters for Clinical Measurements in Radiology David Hintenlang, Ph.D., DABR, FACMP Medical Physics Program Director J. Crayton Pruitt Family Department of Biomedical Engineering J. Crayton Pruitt Family Department of Biomedical Engineering Medical Physics Program Conflict of interest statement: The presenter holds no financial interest in, and has no affiliation or research support from any manufacturer or distributor of MOSFET Dosimetry systems. J. Crayton Pruitt Family Department of Biomedical Engineering Medical Physics Program The MOSFET Dosimeter • Metal oxide silicon field effect transistor • Uniquely packaged to serve as a radiation detector – developed as early as 1974 • Applications – Radiation Therapy Dose Verification – Cosmic dose monitoring on satellites – Radiology • ~ 1998 - present J. Crayton Pruitt Family Department of Biomedical Engineering Medical Physics Program Attractive features • Purely electronic dosimeter • Provides immediate dose feedback • Integrates over short periods of time • Small size and portability • Simultaneous measurements (up to 20) J. Crayton Pruitt Family Department of Biomedical Engineering Medical Physics Program Demonstrated radiology applications – Patient dose monitoring/evaluation • Radiography • Fluoroscopic and interventional procedures • CT • Mammography J. Crayton Pruitt Family Department of Biomedical Engineering Medical Physics Program Principles of operation • Ionizing radiation results in the creation of electron-hole pairs • Holes migrate and build up -
Radiation Survey Meters in Hospitals: Technology, Challenges, and a New Approach
White paper Radiation survey meters in hospitals: technology, challenges, and a new approach This white paper introduces a new radiation sur- essary environmental radiation in hospitals. To vey meter for the hospital segment: the RaySafe lower the risks of unwanted radiation-induced 452. First, the need for survey meters in hospi- effects, the goal is to minimize the exposure to tal environments is described. This is followed unnecessary radiation, both for patients and staff. by an introduction to common survey meter To be able to take the correct measures, it is es- technologies to illustrate their possibilities and sential to know the properties of the radiation in delimitations. Next, some difficulties with survey terms of energy range, dose rate, type of radia- meter measurements in hospitals are identified tion, and more. This is where radiation survey and discussed. Finally, the technology inside the meters are needed. RaySafe 452 is presented to summarize how the instrument addresses the identified issues. Figure 1 illustrates some measurement scenarios and demonstrate the wide range of measurement 1. Why radiation survey meters are need- needs in hospitals. Table 1 gives an overview of ed in hospitals the main areas of application of survey meters in hospitals, with quantities, units, and typical Ionizing radiation is not visible to the human eye. energy ranges of the radiation. It does not smell or make a noise, and you cannot feel it. In the complex and busy environment of a hospital, how can you ensure that patients and staff are not exposed to more ionizing radiation than necessary? Ionizing radiation is utilized for different purposes in medical procedures, with the three main areas being diagnostic imaging, nuclear medicine, and radiotherapy. -
AFRRI Biodosimetry Worksheet
Armed Forces Radiobiology Research Institute Biodosimetry Worksheet (Medical Record of Radiation Dose, Contamination, and Acute Radiation Sickness Response) Reporting Authority (person(s) creating this page of the report) Last name: First name: Country of origin: Unit: Phone: Fax: Email: Location: Date (yymmdd): Time: Casualty Last name: First name: Rank: Country of origin: Parent unit: Parent unit location: Parent unit phone: Unit e-mail: Unit fax: Casualty location: History of presenting injury (conventional and/or radiation): History of previous radiation exposure: Past medical history (general): Medical countermeasures (e.g., antiemetics, transfusion), specify: Administered (where, when, route): Exposure conditions Date of exposure (yymmdd): Exposure location: Time of exposure: Weather conditions (at time of exposure): Exposure results Describe incident: External exposure overview Contamination overview Body exposure: Total Partial Uncertain External contamination: Yes No Shielding confounder: Yes No Internal contamination: Yes No Contaminated wound: Yes No If wound(s) are radiation contaminated, please provide details here: Biodosimetric assays overview Sampling date, time Estimated time Dose Reference radiation quality yymmdd (time) post-exposure (h) (Gy) and dose rate (Gy/min) Time onset of vomiting: Lymphocyte counts or depletion kinetics: Urine bioassay: Cytogenetic biodosimetry: Other: ARS response category overview (maximum grading 0-4; see pages 4 through 6 for guidance) N: C: G: H: = RC: days after radiation exposure: AFRRI -
Experiment "Gamma Dosimetry and Dose Rate Determination" Instruction for Experiment "Gamma Dosimetry and Dose Rate Determination"
TECHNICAL UNIVERSITY DRESDEN Institute of Power Engineering Training Reactor Reactor Training Course Experiment "Gamma Dosimetry and Dose Rate Determination" Instruction for Experiment "Gamma Dosimetry and Dose Rate Determination" Content: 1 .... Motivation 2..... Theoretical Background 2.1... Properties of Ionising Radiation and Interactions of Gamma Radiation 2.2. Detection of Ionising Radiation 2.3. Quantities and Units of Dosimetry 3..... Procedure of the Experiment 3.1. Commissioning and Calibration of the Dosimeter Thermo FH40G 3.2. Commissioning and Calibration of the Dosimeter Berthold LB 133-1 3.3. Commissioning and Calibration of the Dosimeter STEP RGD 27091 3.4. Setup of the Experiment 3.4.1. Measurement of Dose Rate in Various Distances from the Radiation Source 3.4.2. Measurement of Dose Rate behind Radiation Shielding 3.5. Measurement of Dose Rate at the open Reactor Channel 4..... Evaluation of Measuring Results Figures: Fig. 1: Composition of the attenuation coefficient µ of γ-radiation in lead Fig. 2: Design of an ionisation chamber Fig. 3: Classification and legal limit values of radiation protection areas Fig. 4: Setup of the experiment (issued: January 2019) - 1 - 1. Motivation The experiment aims on familiarising with the methods of calibrating different detectors for determination of the dose and the dose rate. Furthermore, the dose rate and the activity in the vicinity of an enclosed source of ionising radiation (Cs-137) will be determined taking into account the background radiation and the measurement accuracy. Additionally, the experiment focuses on the determination of the dose rate of a shielded source as well as on the calculation of the required thickness of the shielding protection layer for meeting the permissible maximum dose rate. -
Appendix B: Recommended Procedures
Recommended Procedures Appendix B Appendix B: Recommended Procedures Appendix B provides recommended procedures for tasks frequently performed in the laboratory. These procedures outline acceptable methods for meeting radiation safety requirements. The procedures are generic in nature, allowing for the diversity of research facilities, on campus. Contamination Survey Procedures Surveys are performed to monitor for the presence of contamination. Minimum survey frequencies are specified on the radiation permit. The surveys should be sufficiently extensive to allow confidence that there is no contamination. Common places to check for contamination are: bench tops, tools and equipment, floors, telephones, floors, door handles and drawer pulls, and computer keyboards. Types of Contamination Removable contamination can be readily transferred from one surface to another. Removable contamination may present an internal and external hazard because it can be picked up on the skin and ingested. Fixed contamination cannot be readily removed and generally does not present a significant hazard unless the material comes loose or is present large enough amounts to be an external hazard. Types of Surveys There are two types of survey methods used: 1) a direct (or meter) survey, and 2) a wipe (or smear) survey. Direct surveys, using a Geiger-Mueller (GM) detector or scintillation probe, can identify gross contamination (total contamination consisting of both fixed and removable contamination) but will detect only certain isotopes. Wipe surveys, using “wipes” such as cotton swabs or filter papers counted on a liquid scintillation counter or gamma counter can identify removable contamination only but will detect most isotopes used at the U of I. Wipe surveys are the most versatile and sensitive method of detecting low-level removable contamination in the laboratory. -
Digital Radiation Monitor Is a Health and Safety Instrument That Measures Alpha, Digital Radiation Monitor Beta, and Gamma Radiation
1 Introduction The Digital Radiation Monitor is a health and safety instrument that measures alpha, Digital Radiation Monitor beta, and gamma radiation. With the Digital Radiation Monitor, you can: • Monitor possible radiation exposure while working near radionuclides (Order Code DRM-BTD) • Ensure compliance with regulatory standards Contents • Check for leakage from X-ray machines and other sources • Screen for environmental contamination or environmental sources of 1 Introduction ............................................................................................................. 2 radioactivity How the DRM Detects Radiation ................................................................. 2 • Connect the Digital Radiation Monitor to a computer or data logger to record 2 Features ................................................................................................................... 3 and tabulate your data The Display................................................................................................... 3 The Switches ................................................................................................4 This manual gives complete instructions for using the Digital Radiation Monitor and The Detector..................................................................................................5 procedures for common applications. The Ports....................................................................................................... 5 3 Operation................................................................................................................ -
Development of Chemical Dosimeters Development Of
SUDANSUDAN ACADEMYAGADEMY OFOF SCIENCES(SAS)SGIENGES(SAS) ATOMICATOMIC ENERGYEhTERGYRESEARCHESRESEARCHES COORDINATIONCOORDII\rATI ON COUNCILCOUNCIL - Development of Chemical Dosimeters A dissertation Submitted in a partial Fulfillment of the Requirement forfbr Diploma Degree in Nuclear Science (Chemistry) By FareedFadl Alla MersaniMergani SupervisorDr K.S.Adam MurchMarch 2006 J - - - CONTENTS Subject Page -I - DedicationDedication........ ... ... ... ... ... ... ... ... ... ... ... ... ... ... ... ... ... ... ... I Acknowledgement ... '" ... ... ... ... ... ... '" ... ... ... ... '" ... '" ....... .. 11II Abstract ... ... ... '" ... ... ... '" ... ... ... ... -..... ... ... ... ... ... ..... III -I Ch-lch-1 DosimetryDosimefry - 1-1t-l IntroductionLntroduction . 1I - 1-2t-2 Principle of Dosimetry '" '" . 2 1-3l-3 DosimetryDosimefiySystems . 3J 1-3-1l-3-l primary standard dosimeters '" . 4 - 1-3-2l-3-Z Reference standard dosimeters ... .. " . 4 1-3-3L-3-3 Transfer standard dosimeters ... ... '" . 4 1-3-4t-3-4 Routine dosimeters . 5 1-4I-4 Measurement of absorbed dose . 6 1-5l-5 Calibration of DosimetryDosimetrvsystemsvstem '" . 6 1-6l-6 Transit dose effects . 8 Ch-2ch-2 Requirements of chemical dosimeters 2-12-l Introduction ... ... ... .............................................. 111l 2-2 Developing of chemical dosimeters ... ... .. ....... ... .. ..... 12t2 2-3 Classification of Dosimetry methods.methods .......................... 14l4 2-4 RequirementsRequiremsnts of ideal chemical dosimeters ,. ... 15 2-5 Types of chemical system . -
The International Commission on Radiological Protection: Historical Overview
Topical report The International Commission on Radiological Protection: Historical overview The ICRP is revising its basic recommendations by Dr H. Smith Within a few weeks of Roentgen's discovery of gamma rays; 1.5 roentgen per working week for radia- X-rays, the potential of the technique for diagnosing tion, affecting only superficial tissues; and 0.03 roentgen fractures became apparent, but acute adverse effects per working week for neutrons. (such as hair loss, erythema, and dermatitis) made hospital personnel aware of the need to avoid over- Recommendations in the 1950s exposure. Similar undesirable acute effects were By then, it was accepted that the roentgen was reported shortly after the discovery of radium and its inappropriate as a measure of exposure. In 1953, the medical applications. Notwithstanding these observa- ICRU recommended that limits of exposure should be tions, protection of staff exposed to X-rays and gamma based on consideration of the energy absorbed in tissues rays from radium was poorly co-ordinated. and introduced the rad (radiation absorbed dose) as a The British X-ray and Radium Protection Committee unit of absorbed dose (that is, energy imparted by radia- and the American Roentgen Ray Society proposed tion to a unit mass of tissue). In 1954, the ICRP general radiation protection recommendations in the introduced the rem (roentgen equivalent man) as a unit early 1920s. In 1925, at the First International Congress of absorbed dose weighted for the way different types of of Radiology, the need for quantifying exposure was radiation distribute energy in tissue (called the dose recognized. As a result, in 1928 the roentgen was equivalent in 1966). -
MIRD Pamphlet No. 22 - Radiobiology and Dosimetry of Alpha- Particle Emitters for Targeted Radionuclide Therapy
Alpha-Particle Emitter Dosimetry MIRD Pamphlet No. 22 - Radiobiology and Dosimetry of Alpha- Particle Emitters for Targeted Radionuclide Therapy George Sgouros1, John C. Roeske2, Michael R. McDevitt3, Stig Palm4, Barry J. Allen5, Darrell R. Fisher6, A. Bertrand Brill7, Hong Song1, Roger W. Howell8, Gamal Akabani9 1Radiology and Radiological Science, Johns Hopkins University, Baltimore MD 2Radiation Oncology, Loyola University Medical Center, Maywood IL 3Medicine and Radiology, Memorial Sloan-Kettering Cancer Center, New York NY 4International Atomic Energy Agency, Vienna, Austria 5Centre for Experimental Radiation Oncology, St. George Cancer Centre, Kagarah, Australia 6Radioisotopes Program, Pacific Northwest National Laboratory, Richland WA 7Department of Radiology, Vanderbilt University, Nashville TN 8Division of Radiation Research, Department of Radiology, New Jersey Medical School, University of Medicine and Dentistry of New Jersey, Newark NJ 9Food and Drug Administration, Rockville MD In collaboration with the SNM MIRD Committee: Wesley E. Bolch, A Bertrand Brill, Darrell R. Fisher, Roger W. Howell, Ruby F. Meredith, George Sgouros (Chairman), Barry W. Wessels, Pat B. Zanzonico Correspondence and reprint requests to: George Sgouros, Ph.D. Department of Radiology and Radiological Science CRB II 4M61 / 1550 Orleans St Johns Hopkins University, School of Medicine Baltimore MD 21231 410 614 0116 (voice); 413 487-3753 (FAX) [email protected] (e-mail) - 1 - Alpha-Particle Emitter Dosimetry INDEX A B S T R A C T......................................................................................................................... -
Dosimeter Comparison Chart
DOSIMETER COMPARISON CHART Instadose®+ Instadose® EPD or APD TLD Dosimeter OSL Dosimeter Dosimeter Dosimeter Dosimeter Cost $ $ $ $$$$ Photon Photon Photon Photon Photon Beta Beta Neutron DEEP - Hp(10) DEEP - Hp(10) Neutron Neutron Measurements SHALLOW - Hp(0.07) SHALLOW - Hp(0.07) DEEP - Hp(10) DEEP - Hp(10) DEEP - Hp(10) SHALLOW - Hp(0.07) SHALLOW - Hp(0.07) SHALLOW - Hp(0.07) EYE - Hp(3) EYE - Hp(3) Read Out Accumulated Accumulated Accumulated Accumulated Accumulated (On-Demand) (On-Demand) (Lab Processing) (Lab Processing) & Dose Rate Unlimited On- Demand Dose Reads Re-Calibration Required Wearer Engagement High High Low Low High Online Management Portal (Website) Provider Dependent NVLAP Highly manual Accreditation process Immediate Online Badge Reassignment Provider Dependent Archiving Dose (Wearer) Meets Legal Highly manual Dose of Record process for meeting Requirements accreditation NO Collection/ Must be collected to Redistribution meet legal dose of Required record requirements Read/View Dose Data on Your Smartphone Automatic (Calendar-set) Dose Reads Wireless Radio Transmission of USB plug-in to PC Dose Data Communication Immediate High Dose Alerts Upon Successful Communication Instadose Dosimeters use direct ion storage (DIS) TLD (Thermoluminescent OSL (Optically EPDs (Electronic Descriptions technology to measure ionizing radiation through Dosimeter) measures Stimulated Personal Dosimeter) interactions that take place between the non- ionizing radiation Luminescence or APDs (Active volatile analog memory cell, which is surrounded exposure by assessing Dosimeter) measures Personal Dosimeter) by a gas filled ion chamber with a floating gate the intensity of visible ionizing radiation makes use of a diode that creates an electric charge enabling ionized light emitted by a crystal exposure when radiation (silicon or PIN, etc.) to particles to be measured by the change in the inside the detector when energy deposited in the detect “charges” induced electric charge created. -
Site-Specific Calibration of the Hanford Personnel Neutron Dosimeter
Gw^HI0n--7 PNL-SA-24010 SITE-SPECIFIC CALIBRATION OF THE HANFORD PERSONNEL NEUTRON DOSIMETER BEC 2 7 mm A. W. Endres Q o 7- L. W. Brackenbush ° f W. V. Baumgartner B. A. Rathbone October 1994 Presented at the Fourth Conference on Radiation Protection and Dosimetry October 23-27, 1994 Orlando, Florida Prepared for the U.S. Department of Energy under Contract DE-AC06-76RLO 1830 Pacific Northwest Laboratory Richland, Washington 99352 DISCLAIMER This report was prepared as an account of work sponsored by an agency of the United States Government. Neither the United States Government nor any agency thereof, nor any of their employees, makes any warranty, express or implied, or assumes any legal liability or responsi• bility for the accuracy, completeness, or usefulness of any information, apparatus, product, or process disclosed, or represents that its use would not infringe privately owned rights. Refer• ence herein to any specific commercial product, process, or service by trade name, trademark, manufacturer, or otherwise does not necessarily constitute or imply its endorsement, recom• mendation, or favoring by the United States Government or any agency thereof. The views and opinions of authors expressed herein do not necessarily state or reflect those of the United States Government or any agency thereof. MUM1TED 4STR1BUTION Or TH« DU^- to u G£ DISCLAIMER Portions of this document may be illegible in electronic image products. Images are produced from the best available original document. SITE-SPECIFIC CALIBRATION OF THE HANFORD PERSONNEL NEUTRON DOSIMETER A. W. Endres, L. W. Brackenbush, W. V. Baumgartner, and B. A. Rathbone Pacific Northwest Laboratory, Richland, Washington 99352 INTRODUCTION A new personnel dosimetry system, employing a standard Hanford thermo• luminescent dosimeter (TLD) and a combination dosimeter with both CR-39 nuclear track and TLD-albedo elements, is being implemented at Hanford.