Lessons Learned in EURADOS Useful for the Dosimetry of Wildlife

Total Page:16

File Type:pdf, Size:1020Kb

Lessons Learned in EURADOS Useful for the Dosimetry of Wildlife LessonsLessons learnedlearned inin EURADOSEURADOS usefuluseful forfor thethe dosimetrydosimetry ofof wildlifewildlife EURADOS Background/History EURADOS Structure Some specific EURADOS activities “relevant” to wildlife dosimetry Rick Tanner (Chairman, EURADOS WG6: Computational Dosimetry Public Heath England, Chilton, Didcot, UK) STAR Workshop, Madrid 2014 1 EURADOSEURADOS e.V.:e.V.: aa sustainablesustainable networknetwork Werner Rühm ( Chairma n) Filip Vanhavere ( Vice-Chairman ) Helmut Schuhmacher (Treasurer) Jean-François Bottollier-Depois (Secretary ) Elena Fantuzzi, Roger Harrison, Joao Alves, Paola Fattibene, Zeljka Knezevic, Maria Antonia Lopez, Sabine Mayer, Saveta Milanic, Stefan Neumaier, Pavel Olko, Hannes Stadtmann, Rick Tanner, Clemens Woda (Council Members and WG Chairs) [Other contributors acknowledged where relevant] STAR Workshop, Madrid 2014 2 StructureStructure ofof EURADOSEURADOS Beneficiaries Dosimetry Dosimetry research community services Industry, Voting Manufacturers Members 1 Associate Supporting Members 2 EC institutions ICRU, IEC, General ISO, IAEA, Assembly 3 EFOMP, etc Working Groups Legend Office Council 4 external assigns internal interacts Chairperson Vice-Chairperson Secretary Treasurer 1 Institutions performing or promoting research 3 Composed of representatives from Voting Members 2 Scientists contributing to EURADOS’ objectives 4 8-12 members, including Chairperson and Vice-Chairperson STAR Workshop, Madrid 2014 3 3 EURADOSEURADOS VotingVoting MembersMembers 59 Voting Members from 28 European countries (Feb 2013) STAR Workshop, Madrid 2014 4 WorkingWorking Groups:Groups: StatusStatus 20132013 Presently EURADOS runs 8 WGs, each consisting of 15 to 30 members WG2: Harmonization of Individual Monitoring in Europe WG3: Environmental Radiation Monitoring WG6: Computational Dosimetry WG7: Internal Dosimetry WG9: Radiation protection Dosimetry in Medicine WG10: Retrospective Dosimetry WG11: High-Energy Radiation Fields WG12: European Medical ALARA Network STAR Workshop, Madrid 2014 5 IntercomparisonsIntercomparisons andand benchmarksbenchmarks (self(self -- supportingsupporting actions)actions) EURADOS Intercomparisons for whole body photon dosemeters (WG2: 2008, 2010, 2012) EURADOS Intercomparison for whole body neutron dosemeters (WG2: 2012) EURADOS Intercomparison for extremity dosemeters (2009) Intercomparison on Monte Carlo modelling of in vivo measurements of lung contamination with a Livermore phantom (WG7 & WG6) EURADOS Intercomparisons of Early Warning Network Systems (WG2: 2006, 2009, 2012) 2nd Intercomparison of the usage of Monte Carlo (WG6, 2004) 1st Intercomparison of the usage of Monte Carlo (WG6, 2000) 3rd European intercomparison exercise on internal dosimetry (1998) Trial performance tests in individual monitoring of external radiation (1998) STAR Workshop, Madrid 2014 6 EURADOS WG2: HARMONIZATION OF INDIVIDUAL MONITORING IN EUROPE. Chair: Joao Alves, ITN, Portugal IntercomparisonIntercomparison 20082008 forfor WholeWhole BodyBody DosemetersDosemeters inin PhotonPhoton FieldsFields T. W. M. Grimbergen, M. Figel, A. M. Romero, H. Stadtmann and A. F. McWhan STAR Workshop, Madrid 2014 7 AllAll HHp(10)(10) resultsresults STAR Workshop, Madrid 2014 8 AllAll HHp(0.07)(0.07) resultsresults STAR Workshop, Madrid 2014 9 EURADOS WG3: ENVIRONMENTAL RADIATION MONITORING Chair: Stefan Neumaier, PTB, Germany EURADOSEURADOS WG3WG3 intercomparisonsintercomparisons andand thethe harmonizationharmonization ofof environmentalenvironmental radiationradiation monitoringmonitoring S. Neumaier and H. Dombrowski Physikalisch-Technische Bundesanstalt (PTB), Bundesallee 100, 38116 Braunschweig, Germany STAR Workshop, Madrid 2014 10 Radioactive plumes and large scale contaminations in Europe RadioactiveRadioactive plumsplums STAR Workshop, Madrid 2014 11 STAR Workshop, Madrid 2014 12 Early warning dosimetry network stations in Europe About 4700 stations … …provide dose rate data to EURDEP and hence to EC on an hourly basis! Real time dose rate data are of key importance for the ECURIE-systems! STAR Workshop, Madrid 2014 S. Neumaier, PTB 6.3 13 13 -430 m: „radiation free“ environment cosmic radiation Monitoring of „radioactive plume“ simulation cosmic- & terrestrial radiation STAR Workshop, Madrid 2014 14 r Response to cosmic radiation: SCR Cosmic component at the platform 70 -1 60 50 40 30 20 Dose rate instruments 10 PTB reference value H*(10) doserate nSv·h / 0 001/ 002/ 082/ 091/ 113/ 122/ 081/ 112/ 121/ 123/ 101/ 102/ 111/ 083/ IC IC IC IC IC IC GM GM GM GM PC PC PC PSc Instrument r R R H SCR = ( platform - B)/ *(10) SCR H ±±± -1 PTB reference value: *(10) SCR = (36 3) nSv h STAR Workshop, Madrid 2014 15 PlumePlume simulation:simulation: ResultsResults 081/GM 091/IC 200 200 180 180 -1 160 -1 160 140 140 120 120 100 100 80 80 60 60 H*(10) rate / nSv·h H*(10) rate / nSv·h 40 40 20 20 0 0 16:30 18:00 19:30 21:00 22:30 00:00 01:30 03:00 04:30 06:00 07:30 09:00 10:30 16:30 18:00 19:30 21:00 22:30 00:00 01:30 03:00 04:30 06:00 07:30 09:00 10:30 113/IC 121/GM 200 200 180 180 160 -1 160 -1 140 140 120 120 100 100 80 80 60 60 H*(10) rate / nSv ·h 40 H*(10) rate 7 nSv·h 40 20 20 0 0 16:30 18:00 19:30 21:00 22:30 00:00 01:30 03:00 04:30 06:00 07:30 09:00 10:30 16:30 18:00 19:30 21:00 22:30 00:00 01:30 03:00 04:30 06:00 07:30 09:00 10:30 STAR Workshop, Madrid 2014 16 EURADOS WG6: COMPUTATIONAL DOSIMETRY Chair: Rick Tanner, PHE, UK CONSTRUCTION OF VOXEL MODELS FROM 3D MEDICAL IMAGE DATA Maria Zankl, HGMU, Germany STAR Workshop, Madrid 2014 17 Construction of voxel models from 3D medical image data Image processing software Original CT slice Segmented slice Grey values: absorption Colours: identification properties numbers assigned to individual organs STAR Workshop, Madrid 2014 18 Segmentation • Identifying individual organs in all slices • Assigning appropriate organ identification numbers to all pixels in all slices • Easy for • Tissues with high contrast (use grey value thresholds) • Small body sections (often: manual drawing of organ boundaries) • Difficult in all other cases due to • Large range of grey values within individual organs • Largely overlapping grey values ranges between organs • Large number of organs and slices to be segmented STAR Workshop, Madrid 2014 19 Segmented data Stack of slices → 3D array of volume elements (voxel) Data per slice arranged in columns and rows of picture elements (pixel) Visible Irene Human Golem STAR Workshop, Madrid 2014 20 w T – development Organ 1977 1990 2007 Gonads 0.25 0.20 0.08 Remainder Bone marrow (red) 0.12 0.12 0.12 ICRP60 : adrenals, brain, Lung 0.12 0.12 0.12 upper large intestine, Breast 0.15 0.05 0.12 small intestine, kidney, Thyroid 0.03 0.05 0.04 muscle, pancreas, spleen, Bone surfaces 0.03 0.01 0.01 thymus and uterus Remainder 0.30 0.05 0.12 Colon - 0.12 0.12 ICRP103 : adrenals, Stomach - 0.12 0.12 extrathoracic tissue, gall bladder, heart wall, Bladder - 0.05 0.04 kidneys, lymph nodes, Liver - 0.05 0.04 muscle, oral mucosa, Oesophagus - 0.05 0.04 pancreas, prostate, small Skin - 0.01 0.01 intestine, spleen, thymus, Salivary glands - - 0.01 uterus/cervix Brain - - 0.01 STAR Workshop, Madrid 2014 21 WG7: INTERNAL DOSIMETRY & WG6: COMPUTATIONAL DOSIMETRY EURADOS WG6/7 INTERCOMPARISON EXERCISE ON MC MODELLING FOR THE IN - VIVO MONITORING OF AM -241 IN SKULL PHANTOMS (PART I). Tomas Vrba, Pedro Nogueira, David Broggio, Margarida Caldeira, Kevin Capello, Karin Fantínová, Catarina de Sousa Figueira, John Hunt, Debora Leone, Manohari Murugan, Olaf Marzocchi, Montse Moraleda, Jakub Osko, Arron Shutt, Soheigh Suh, Masa Takahashi, Maria A. Lopez, Rick Tenner STAR Workshop, Madrid 2014 22 IntroductionIntroduction toto inin --vivovivo measurementmeasurement methodmethod calibration phantom Detection MC simulation system spectrum subject activity subject (Bq) STAR Workshop, Madrid 2014 23 GeometryGeometry STAR Workshop, Madrid 2014 24 DeviationDeviation fromfrom thethe measurementmeasurement –– beforebefore correctioncorrection STAR Workshop, Madrid 2014 25 ObservedObserved errorerror inin simulationsimulation STAR Workshop, Madrid 2014 26 DeviationDeviation fromfrom thethe measurementmeasurement –– afterafter correctioncorrection STAR Workshop, Madrid 2014 27 RelativeRelative detectiondetection efficiencyefficiency atat 59.5459.54 keVkeV Maximal difference from the GM < ±5% STAR Workshop, Madrid 2014 28 EURADOS WG7: INTERNAL DOSIMETRY Chair: Maria Antonia Lopez, CIEMAT, Spain Toxicology of the actinides used in the nuclear industry Dose estimates based on numerical methods - Ongoing projects at the Radiation Toxicology Laboratory, CEA, France Stéphanie Lamart « Some of the results presented in this Radiation Toxicology Laboratory document were obtained in the frame of a collaboration agreementFrench with AlternativeAREVA. The Energies and Atomic Energy Commission (CEA) release of this document falls under the rules of this agreement » Note: wolf dosimetry contribution from David Broggio (IRSN) omitted following presentation from Tom Hinton (IRSN) STAR Workshop, Madrid 2014 | PAGE 29 29 RadiationRadiation ToxicologyToxicology LaboratoryLaboratory Research objectives and activities • To characterize the biokinetics of radionuclides (actinides) • Transfer rates between biological compartments • Retention in tissues • Excretion • To study the radiation toxicity • To develop treatment strategies Experimental methods Treatment Contamination Urine • Spectrometry Faeces • Pu isotopes, Am-241 Tissues • Histology • Inhalation or wound Rat model STAR Workshop, Madrid
Recommended publications
  • 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).
    [Show full text]
  • 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.........................................................................................................................
    [Show full text]
  • 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.
    [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]
  • 11. Dosimetry Fundamentals
    Outline • Introduction Dosimetry Fundamentals • Dosimeter model • Interpretation of dosimeter measurements Chapter 11 – Photons and neutrons – Charged particles • General characteristics of dosimeters F.A. Attix, Introduction to Radiological Physics and Radiation Dosimetry • Summary Introduction Dosimeter • Radiation dosimetry deals with the determination • A dosimeter can be generally defined as (i.e., by measurement or calculation) of the any device that is capable of providing a absorbed dose or dose rate resulting from the interaction of ionizing radiation with matter reading R that is a measure of the absorbed • Other radiologically relevant quantities are dose Dg deposited in its sensitive volume V exposure, kerma, fluence, dose equivalent, energy by ionizing radiation imparted, etc. can be determined • If the dose is not homogeneous • Measuring one quantity (usually the absorbed dose) another one can be derived through throughout the sensitive calculations based on the defined relationships volume, then R is a measure of mean value Dg Dosimeter Simple dosimeter model • Ordinarily one is not interested in measuring • A dosimeter can generally be considered as the absorbed dose in a dosimeter’s sensitive consisting of a sensitive volume V filled with a volume itself, but rather as a means of medium g, surrounded by a wall (or envelope, determining the dose (or a related quantity) for container, etc.) of another medium w having a another medium in which direct measurements thickness t 0 are not feasible • A simple dosimeter can be
    [Show full text]
  • Radiation Dosimetry in Cases of Normal and Emergency Situations
    Radiation Dosimetry in Cases of Normal and Emergency Situations A Thesis Submitted to Department of Physics Faculty of Science, Al Azhar University for The Degree of PhD. in Physics by Tarek Mahmoud Morsi M.Sc. (Physics, 2003) Radiation Protection Department, Nuclear Research Center, Atomic Energy Authority Under Supervision Emeritus Prof. M. I. El Gohary Emeritus Prof. M. A. Gomaa Prof. of Biophysics Prof. of Radiation Physics Al Azhar University Atomic Energy Authority Emeritus Prof. Samia M. Rashad Emeritus Dr. Eid M. Ali Prof. of Radiation Emergencies Lecturer of Radiation Physics Atomic Energy Authority Atomic Energy Authority 2010 Approval Sheet for Submission Ti tle of the PhD. Thesis Radiation Dosimetry in Cases of Normal and Emergency Situations Name of the Candidate Tarek Mahmoud Morsi Atomic Energy Authority This thesis has been approved for submission by the supervisors : Emeritus Prof. M. I. El Gohary Emeritus Prof. M. A. Gomaa Prof. of Biophysics Prof. of Radiation Physics Al Azhar University Atomic Energy Authority Emeritus Prof. Samia M. Rashad Emeritus Dr. Eid M. Ali Prof. of Radiation Emergencies Lecturer of Radiation Physics Atomic Energy Authority Atomic Energy Authority Acknowledgement First and above all, all thanks to ALLAH the Merciful, the Compassionate without his help. I couldn't finish this work. I wish to express my sincere thanks and gratitude to Professor Dr. Mohamed I. EL-Gohary, Prof. of Biophysics, faculty of science, Al- Azhar University and Professor Dr. Mohamed A. Gomaa, Prof. of Radiation Physics, Atomic Energy Authority (A.E.A) for their kind supervision, continuous encouragement and helps during the course of this work.
    [Show full text]
  • Chapter 3: Radiation Dosimeters
    Chapter 3: Radiation Dosimeters Set of 113 slides based on the chapter authored by J. Izewska and G. Rajan of the IAEA publication: Review of Radiation Oncology Physics: A Handbook for Teachers and Students Objective: To familiarize the student with the most important types and properties of dosimeters used in radiotherapy Slide set prepared in 2006 by G.H. Hartmann (Heidelberg, DKFZ) Comments to S. Vatnitsky: [email protected] IAEA International Atomic Energy Agency CHAPTER 3. TABLE OF CONTENTS 3.1 Introduction 3.2 Properties of dosimeters 3.3 Ionization chamber dosimetry systems 3.4 Film dosimetry 3.5 Luminescence dosimetry 3.6 Semiconductor dosimetry 3.7 Other dosimetry systems 3.8 Primary standards 3.9 Summary of commonly used dosimetry systems IAEA Review of Radiation Oncology Physics: A Handbook for Teachers and Students - 3. 1 3.1 INTRODUCTION Historical Development of Dosimetry: Some highlights 1925: First International Congress for Radiology in London. Foundation of "International Commission on Radiation Units and Measurement" (ICRU) 1928: Second International Congress for Radiology in Stockholm. Definition of the unit “Roentgen” to identify the intensity of radiation by the number of ion pairs formed in air. 1937: Fifth International Congress for Radiology in Chicago. New definition of Roentgen as the unit of the quantity "Exposure". IAEA Review of Radiation Oncology Physics: A Handbook for Teachers and Students - 3.1 Slide 1 3.1 INTRODUCTION Definition of Exposure and Roentgen Exposure is the quotient of ΔQ by Δm where • ΔQ is the sum of the electrical charges on all the ions of one sign produced in air, liberated by photons in a volume element of air and completely stopped in air • Δm is the mass of the volume element of air The special unit of exposure is the Roentgen (R).
    [Show full text]
  • Personal Radiation Dosimetry Policy Number 1988-## (11-025)
    PERSONAL RADIATION DOSIMETRY POLICY NUMBER 1988-## (11-025) A. Effective Date: Approved by RSC 12/7/18 B. PURPOSE: To maintain occupational radiation exposure to personnel as low as reasonably achievable (ALARA) and ensure compliance with all federal, state and other Agency requirements regarding the monitoring of employed, contracted, affiliate, or trainee personnel who may be occupationally exposed to external sources of ionizing radiation, such as radioactive material (RAM) or radiation generating devices (RGD), while present at UConn Health, any UConn Health off-site facility, or affiliated sites. C. POLICY: a. Personal radiation dosimeters will be provided to personnel as specified by State of Connecticut and/or Nuclear Regulatory Commission requirements and/or as deemed necessary and appropriate by the Radiation Safety Officer (RSO) or designee. b. Residents/fellows must follow UConn Radiation Safety procedure ‘Procedures for Residents and Fellows Provided Personal Radiation Dosimetry from UConn Health’. All other personnel must follow UConn Radiation Safety procedure ‘Personal Radiation Dosimetry Procedures for UConn Health Personnel’. c. Personnel are responsible for the physical control of all assigned dosimetry. • When dosimetry is issued, the wearer accepts responsibility for the assigned dosimeter and shall be responsible for replacement costs outlined in the lost, damaged, or accidently exposed dosimetry section of the applicable procedure (i.e., ‘Procedures for Residents and Fellows Provided Personal Radiation Dosimetry from UConn Health’ or ‘Personal Radiation Dosimetry Procedures for UConn Health Personnel’). d. Personnel’s dosimetry records are confidential and will only be released with a signed consent. e. Personnel identified as requiring personal radiation monitoring by the RSO or designee will not work in areas where dosimetry is required until a badge has been issued.
    [Show full text]
  • Dosimetry for Food Irradiation
    Technical Reports Series No. 409 Dosimetry for Food Irradiation INTERNATIONAL ATOMIC ENERGY AGENCY, VIENNA, 2002 DOSIMETRY FOR FOOD IRRADIATION The following States are Members of the International Atomic Energy Agency: AFGHANISTAN GHANA PANAMA ALBANIA GREECE PARAGUAY ALGERIA GUATEMALA PERU ANGOLA HAITI PHILIPPINES ARGENTINA HOLY SEE POLAND ARMENIA HUNGARY PORTUGAL AUSTRALIA ICELAND QATAR AUSTRIA INDIA REPUBLIC OF MOLDOVA AZERBAIJAN INDONESIA ROMANIA BANGLADESH IRAN, ISLAMIC REPUBLIC OF RUSSIAN FEDERATION BELARUS IRAQ SAUDI ARABIA BELGIUM IRELAND SENEGAL BENIN ISRAEL SIERRA LEONE BOLIVIA ITALY SINGAPORE BOSNIA AND HERZEGOVINA JAMAICA SLOVAKIA BOTSWANA JAPAN SLOVENIA BRAZIL JORDAN SOUTH AFRICA BULGARIA KAZAKHSTAN SPAIN BURKINA FASO KENYA SRI LANKA CAMBODIA KOREA, REPUBLIC OF SUDAN CAMEROON KUWAIT SWEDEN CANADA LATVIA SWITZERLAND CENTRAL AFRICAN LEBANON SYRIAN ARAB REPUBLIC REPUBLIC LIBERIA TAJIKISTAN CHILE LIBYAN ARAB JAMAHIRIYA THAILAND CHINA LIECHTENSTEIN THE FORMER YUGOSLAV COLOMBIA LITHUANIA REPUBLIC OF MACEDONIA COSTA RICA LUXEMBOURG TUNISIA CÔTE D’IVOIRE MADAGASCAR TURKEY CROATIA MALAYSIA UGANDA CUBA MALI UKRAINE CYPRUS MALTA UNITED ARAB EMIRATES CZECH REPUBLIC MARSHALL ISLANDS UNITED KINGDOM OF DEMOCRATIC REPUBLIC MAURITIUS GREAT BRITAIN AND OF THE CONGO MEXICO NORTHERN IRELAND DENMARK MONACO UNITED REPUBLIC DOMINICAN REPUBLIC MONGOLIA OF TANZANIA ECUADOR MOROCCO UNITED STATES OF AMERICA EGYPT MYANMAR URUGUAY EL SALVADOR NAMIBIA UZBEKISTAN ESTONIA NETHERLANDS VENEZUELA ETHIOPIA NEW ZEALAND VIET NAM FINLAND NICARAGUA YEMEN FRANCE NIGER YUGOSLAVIA, GABON NIGERIA FEDERAL REPUBLIC OF GEORGIA NORWAY ZAMBIA GERMANY PAKISTAN ZIMBABWE The Agency’s Statute was approved on 23 October 1956 by the Conference on the Statute of the IAEA held at United Nations Headquarters, New York; it entered into force on 29 July 1957. The Headquarters of the Agency are situated in Vienna.
    [Show full text]
  • Spectrometry and Dosimetry of a Neutron Source
    X International Symposium/XX National Congress on Solid State Dosimetry “Augusto Moreno y Moreno” September 24-27; 2007. Puebla, Pue. Mexico SPECTROMETRY AND DOSIMETRY OF A NEUTRON SOURCE Héctor René Vega-Carrillo*/**, Eduardo Manzanares-Acuña*, Víctor M. Hernández-Dávila*/**, Jaime Ramírez González*, Rubén Hernández Villasana*, Alejandro Chacón Ruiz*/** Unidades Académicas de *Estudios Nucleares e **Ingeniería Eléctrica Universidad Autónoma de Zacatecas C. Ciprés 10, Fracc. La Peñuela, 98068 Zacatecas, Zac. México [email protected] Resumen Using Monte Carlo methods the spectrum, dose equivalent and ambient dose equivalent of a 239PuBe at several distances has been determined. Spectrum and both doses, at 100 cm, were determined experimentally using a Bonner sphere spectrometer. These quantities were obtained by unfolding the spectrometer count rates using artificial neural networks. The dose equivalent, based in the ICRP 21 criteria, was measured with the area neutron dosemeter Eberline model NRD, at 100, 200 and 300 cm. All measurements were carried out in an open space to avoid the room return. With these results it was found that this source has a yield of 8.41E(6) n/s. Keywords: Spectrum, Dose, Neutron source, Monte Carlo Memorias CDES en CDROM 1/10 Proceedings SSSD on CDROM Vega-Carrillo, H.R. et al. Spectrometry and dosimetry of a neutron source 1. INTRODUCTION In 1932, Chadwick did show the existence of neutron [1, 2]; since then neutrons have been widely utilized in science and technology. Neutrons are artificially produced by nuclear fission and nuclear fusion in reactors, using accelerating devices that induce nuclear reactions involving charged particles and gamma-rays, and with alpha and gamma radiations from radioactive nuclides.
    [Show full text]
  • Bq = Becquerel Gy = Gray (Sv = Sievert)
    Louis Harold Gray He is honored by call- ing the physical dose Bq = becquerel unit "gray*" – abbrevi- Gy = gray ated Gy (Sv = sievert) Photo from 1957 Chapter 5 Activity and Dose The activity of a radioactive source When an atom disintegrates, radiation is emitted. If the rate of disintegrations is large, the radioactive source is considered to have a high activity. The unit for the activity of a radioactive source was named after Becquerel (abbreviated Bq) and is defined as: 1 Bq = 1 disintegration per sec. In a number of countries, the old unit, the curie (abbreviated Ci and named after Marie and Pierre Curie) is still used. The curie-unit was defined as the activity in one gram of radium. The number of disintegrations per second in one gram of radium is 37 billion. The relation between the curie and the becquerel is given by: 1 Ci = 3.7 • 1010 Bq The accepted practice is to give the activity of a radioactive source in becquerel. This is because Bq is the unit chosen for the system of international units (SI-units). But one problem is that the numbers in becquerel are always very large. Consequently the activity is given in kilo (103), mega (106), giga (109)and tera (1012) becquerel. If a source is given in curies the number is small. For example; when talking about radioactivity in food products, 3,700 Bq per kilogram of meat is a large number and consequently considered to be dangerous. If however, the same activity is given in Ci, it is only 0.0000001 curie per kilogram – "nothing to worry about?".
    [Show full text]
  • Radiation Survey Meter – How It Works Detecting Radiation
    Radiation Survey Meter – How it Works Detecting Radiation Radiation can be detected using a variety of instruments and methods that read out in exposure or count rate. The measuring device used is dependent upon the type of radiation and the measurement needed. The three basic methods employed involve the use of survey instruments, liquid scintillation counters and dosimetry. This section discusses the operation of the two most common types of survey instruments used for the detection of ionizing radiation. Survey Instruments Survey instruments locate contamination or detect radioactive material. Radioactive material detected in the attached probe causes electronic pulses that move the meter needle and make an audio response. The meters read out in counts per minute (cpm) and can be calibrated to report mR/hr. There is a large selection of survey instruments available, designed for the detection of a specific type of radiation. One of the most common survey meters, shown here, can be used with various probes, depending on your needs and radionuclide. Before using a survey meter, make sure you have the right probe, such as pancake (Geiger Mueller) or scintillation (Sodium-Iodide) Probe. GM Probe with Survey Meter The GM Probe has a simple construction. Just under the surface, you can see a gas filled chamber connected to a simple circuit. Radiation interacts in the chamber and is changed into an electronic pulse. Laboratory Safety 46 Blackstone Street, Cambridge, MA 02139 | T: 617.496.3797 | F: 617.496.5509 www.ehs.harvard.edu | email: [email protected] The screen protects the thin-film window from breakage, scratches, or puncture.
    [Show full text]