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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. -
THESIS VERIFICATION of BACKGROUND REDUCTION in a LIQUID SCINTILLATION COUNTER Submitted by Marilyn Alice Magenis Department of E
THESIS VERIFICATION OF BACKGROUND REDUCTION IN A LIQUID SCINTILLATION COUNTER Submitted by Marilyn Alice Magenis Department of Environmental and Radiological Health Sciences In partial fulfillment of the requirements For the Degree of Master of Science Colorado State University Fort Collins, Colorado Summer 2013 Master’s Committee: Advisor: Alexander Brandl Thomas E. Johnson John Volckens John Harton ABSTRACT VERIFICATION OF BACKGROUND REDUCTION IN A LIQUID SCINTILLATION COUNTER A new method for subtraction of extraneous cosmic ray background counts from liquid scintillation detection has been developed by HidexTM. The method uses a background counter located beneath the liquid scintillation detector, the guard, to account for background signals. A double to triple coincidence counting methodology is used to reduce photomultiplier noise and to quantify quench. It is important to characterize the interactions from background in any new system. Characterizing interactions in the instrument will help to verify the accuracy and efficiency of the guard by determining the noise cancellation capabilities of the liquid scintillation counter. The liquid scintillation counter and guard detector responses were modeled using MCNP for the expected cosmic ray interactions at the instrument location and altitude in Fort Collins, CO. Cosmic ray interactions in the detector are most relevant to examine because of their predominance due to the higher elevation in Fort Collins. The cosmic ray interactions that are most important come from electron, positron, and gamma interactions. The expected cosmic ray interactions from these particles were modeled by using a cosmic ray library that determines the cosmic rays that are most likely to occur at an altitude of 2100 meters. -
Evaluation of Fernald
Draft ADVISORY BOARD ON RADIATION AND WORKER HEALTH National Institute for Occupational Safety and Health Review of the General Steel Industries Special Exposure Cohort (SEC) Petition-00105 and the NIOSH SEC Petition Evaluation Report Contract No. 200-2009-28555 SCA-SEC-TASK5-0005 Prepared by S. Cohen & Associates 1608 Spring Hill Road, Suite 400 Vienna, Virginia 22182 July 2009 [Redacted version – October 2, 2009] Disclaimer This document is made available in accordance with the unanimous desire of the Advisory Board on Radiation and Worker Health (ABRWH) to maintain all possible openness in its deliberations. However, the ABRWH and its contractor, SC&A, caution the reader that at the time of its release, this report is pre-decisional and has not been reviewed by the Board for factual accuracy or applicability within the requirements of 42 CFR 82. This implies that once reviewed by the ABRWH, the Board’s position may differ from the report’s conclusions. Thus, the reader should be cautioned that this report is for information only and that premature interpretations regarding its conclusions are unwarranted. Effective Date: Revision No.: Document No.: Page No.: July 24, 2009 0 SCA-SEC-TASK5-0005 Page 2 of 50 S. COHEN & ASSOCIATES: Document No. SCA-SEC-TASK5-0005 Technical Support for the Advisory Board on Effective Date: Radiation & Worker Health Review of July 24, 2009 – Draft NIOSH Dose Reconstruction Program Redacted version – October 2, 2009 Revision No. 0 Review of the General Steel Industries Special Exposure Cohort (SEC) Petition-00105 -
A Standard Complex-Wide Methodology for Overestimating External Doses Effective Date: 06/05/2006 Measured with Film Badge Dosimeters Type of Document: OTIB
ORAU TEAM Dose Reconstruction Project for NIOSH Oak Ridge Associated Universities I Dade Moeller & Associates I MJW Corporation Page 1 of 19 Document Title: Document Number: ORAUT-OTIB-0010 Revision: 01 A Standard Complex-Wide Methodology for Overestimating External Doses Effective Date: 06/05/2006 Measured with Film Badge Dosimeters Type of Document: OTIB Supersedes: Revision 00 Subject Experts: Donald N. Stewart and Jack J. Fix Document Owner Approval: Signature on File Approval Date: 05/17/2006 James P. Griffin, Deputy Project Director Concurrence: Signature on File Concurrence Date: 05/22/2006 Kate Kimpan, Project Director Approval: Signature on File Approval Date: 06/05/2006 James W. Neton, Associate Director for Science New Total Rewrite Revision Page Change FOR DOCUMENTS MARKED AS A TOTAL REWRITE, REVISION, OR PAGE CHANGE, REPLACE THE PRIOR REVISION AND DISCARD / DESTROY ALL COPIES OF THE PRIOR REVISION. Document No. ORAUT-OTIB-0010 Revision No. 01 Effective Date: 06/05/2006 Page 2 of 19 PUBLICATION RECORD EFFECTIVE REVISION DATE NUMBER DESCRIPTION 01/12/2004 00 New Technical Information Bulletin for a Standard Complex-Wide Correction Factor for Overestimating External Doses Measured with Film Badge Dosimeters. First approved issue. Initiated by Donald N. Stewart. 06/05/2006 01 Constitutes rewrite of document as a result of biennial review. Incorporates resolution of S. Cohen & Associates final draft comments contained in “The Review of NIOSH/ORAUT Procedures and Methods used for Dose Reconstruction” (ref: letter from John Mauro to David Staudt, dated January 17, 2005). Approved issue of Revision 01. This revision results in no change to the assigned dose and no PER is required. -
Liquid Scintillation Counting
Institutionen för medicin och vård Avdelningen för radiofysik Hälsouniversitetet Liquid Scintillation Counting Sten Carlsson Department of Medicine and Care Radio Physics Faculty of Health Sciences Series: Report / Institutionen för radiologi, Universitetet i Linköping; 78 ISSN: 1102-1799 ISRN: LIU-RAD-R-078 Publishing year: 1993 © The Author(s) Report 78 lSSN 1102-1799 Nov 1993 lSRN ULI-RAD-R--78--SE Liquid Scintillation Counting Sten Carlsson Dept of Radiation Physlcs Dept Medical Physlcs Linköping Unlverslly , Sweden: UddevalIa,Svveden i 1. INTRODUCTIQN In liquid scintillation counting (LSC) we use the process ofluminescense to detect ionising radiation emit$ed from a radionuclide. Luminescense is emission of visible light ofnon thermal origin. 1t was early found that certain organic molecules have luminescent properties and such molecules are used in LSC. Today LSC is the mostwidespread method to detect pure beta-ernitters like tritium and carbon-14. 1t has unique properties in its efficient counting geometry, deteetability and the lack of any window which the beta particles have to penetrate. These properties are achieved by solving the sample to measure in a scintillation cocktail composed of an organic solvent and a solute (scintillator). Even if LSC is a weil established measurement technique, the user can run into problems and abasic knowledge of the deteetor and its different components is offundamental importance in a correct use of the technique. The alm of this presentation is to provide the user with some of this fundamental knowledge. 2. BAS1C PRINCIPLE LSC is based on the principle oftransformlng some of the kinetic energy of the beta-partic1e into light photons. -
Radiation Safety Guide Research Use of Radioactive Materials
Radiation Safety Guide Research Use of Radioactive Materials Table of Contents Page RADIATION AND RADIOACTIVITY 4 A. Decay by Alpha (α)-Particle Emission 4 B. Decay by Beta (β)− Particle Emission 5 C. Decay by Gamma Ray (γ) emission 5 D. Decay by Electron Capture (X-ray) 5 E. Other sources of Radiation 5 F. Neutron particles (n) 6 G. Radiation Quantities 6 H. Half-life, Biological half-life, Effective half-life 7 I. Radiation Detection Instrument 8 1. Gas-filled detectors 8 2. Scintillation Detector 8 J. Background Radiation 9 K. Biological Effect of Radiation 10 PRINCIPLES OF RADIATION SAFETY 11 A. Occupational Dose Limit 11 B. Public Dose 11 D. Dose to an Embryo/Fetus 11 E. Registration of Radiation Workers 12 F. Personnel Monitoring 12 G. Type of Dosimeters 12 H. Dosimeter Placement 12 I. Internal Monitoring 13 J. Exposure Reports 13 K. ALARA 13 L.Posting 14 1 RADIATION SAFETY PROGRAM 16 A. Individuals Responsible For Radiation Safety Program 16 B. Organization Chart 16 C. Radiation Safety Committee 16 D. Radiation Safety Officer 17 E. Authorized Users 18 F. Radiation Workers 19 G. Radioactive Drug Research Committee (RDRC) 19 H. Medical Radiation Subcommittee (MRC) 22 RADIATION SAFETY PROCEDURES 23 A. Training Program 23 1. Initial Radiation Safety Training 24 2. Annual Refresher Training 24 3. Radiation Safety Training for Clinical Staff 24 4. Radiation Safety Training for House Keeping, Physical Plant and Security Staff 24 5. Radiation Safety Training for irradiator workers 24 B. Audit Program 24 C. Survey Program 25 1. Survey for Removable Contamination 27 2. -
Lumi-Scint Liquid Scintillation Counter
DOE/EM-0596 Lumi-Scint Liquid Scintillation Counter Deactivation and Decommissioning Focus Area Prepared for U.S. Department of Energy Office of Environmental Management Office of Science and Technology July 2001 Lumi-Scint Liquid Scintillation Counter OST/TMS ID 2311 Deactivation and Decommissioning Focus Area Demonstrated at Miamisburg Environmental Management Project Miamisburg, Ohio Purpose of this document Innovative Technology Summary Reports are designed to provide potential users with the information they need to quickly determine if a technology would apply to a particular environmental management problem. They are also designed for readers who may recommend that a technology be considered by prospective users. Each report describes a technology, system, or process that has been developed and tested with funding from DOE’s Office of Science and Technology (OST). A report presents the full range of problems that a technology, system, or process will address and its advantages to the DOE cleanup in terms of system performance, cost, and cleanup effectiveness. Most reports include comparisons to baseline technologies as well as other competing technologies. Information about commercial availability and technology readiness for implementation is also included. Innovative Technology Summary Reports are intended to provide summary information. References for more detailed information are provided in an appendix. Efforts have been made to provide key data describing the performance, cost, and regulatory acceptance of the technology. If this information was not available at the time of publication, the omission is noted. All published Innovative Technology Summary Reports are available on the OST website at www.em.doe.gov/ost under “Publications.” TABLE OF CONTENTS 1. -
ORAU Team Document Number: ORAUT-TKBS-0008-6
ORAU Team Document Number: ORAUT-TKBS-0008-6 Dose Reconstruction Project for NIOSH Effective Date: 09/21/2004 Revision No.: 00 Technical Basis Document for the Nevada Test Site – Controlled Copy No.: ________ Occupational External Dose Page 1 of 55 Subject Expert: Eugene M. Rollins Supersedes: Document Owner Approval: Signature on File Date: 09/16/2004 Eugene M. Rollins, TBD Team Leader None Approval: Signature on File Date: 09/16/2004 Judson L. Kenoyer, Task 3 Manager Concurrence: Signature on File Date: 09/13/2004 Richard E. Toohey, Project Director Approval: Signature on File Date: 09/21/2004 James W. Neton, Associate Director for Science TABLE OF CONTENTS Section Page Record of Issue/Revisions ................................................................................................................... 4 Acronyms and Abbreviations ............................................................................................................... 5 6.1 Introduction ................................................................................................................................. 7 6.2 Dosimetric Basis of Comparison ................................................................................................. 7 6.2.1 Photon Measurement Quantities ........................................................................................ 8 6.2.2 Beta Measurement Quantities ............................................................................................ 9 6.2.3 Neutron Measurement Quantities ...................................................................................... -
Radiation Safety
RADIATION SAFETY FOR LABORATORY WORKERS RADIATION SAFETY PROGRAM DEPARTMENT OF ENVIRONMENTAL HEALTH, SAFETY AND RISK MANAGEMENT UNIVERSITY OF WISCONSIN-MILWAUKEE P.O. BOX 413 LAPHAM HALL, ROOM B10 MILWAUKEE, WISCONSIN 53201 (414) 229-4275 SEPTEMBER 1997 (REVISED FROM JANUARY 1995 EDITION) CHAPTER 1 RADIATION AND RADIOISOTOPES Radiation is simply the movement of energy through space or another media in the form of waves, particles, or rays. Radioactivity is the name given to the natural breakup of atoms which spontaneously emit particles or gamma/X energies following unstable atomic configuration of the nucleus, electron capture or spontaneous fission. ATOMIC STRUCTURE The universe is filled with matter composed of elements and compounds. Elements are substances that cannot be broken down into simpler substances by ordinary chemical processes (e.g., oxygen) while compounds consist of two or more elements chemically linked in definite proportions. Water, a compound, consists of two hydrogen and one oxygen atom as shown in its formula H2O. While it may appear that the atom is the basic building block of nature, the atom itself is composed of three smaller, more fundamental particles called protons, neutrons and electrons. The proton (p) is a positively charged particle with a magnitude one charge unit (1.602 x 10-19 coulomb) and a mass of approximately one atomic mass unit (1 amu = 1.66x10-24 gram). The electron (e-) is a negatively charged particle and has the same magnitude charge (1.602 x 10-19 coulomb) as the proton. The electron has a negligible mass of only 1/1840 atomic mass units. The neutron, (n) is an uncharged particle that is often thought of as a combination of a proton and an electron because it is electrically neutral and has a mass of approximately one atomic mass unit. -
The Use of Film Badges for Personnel Monitoring
This publication is not longer valid Please see http://www-ns.iaea.org/standards/ SAFETY SERIES No. 8 The Use of Film Badges for Personnel Monitoring INTERNATIONAL ATOMIC ENERGY AGENCY, VIENNA, 1962 This publication is not longer valid Please see http://www-ns.iaea.org/standards/ This publication is not longer valid Please see http://www-ns.iaea.org/standards/ THE USE OF FILM BADGES FOR PERSONNEL MONITORING This publication is not longer valid Please see http://www-ns.iaea.org/standards/ The following States are Members of the International Atomic Energy Agency: AFGHANISTAN ISRAEL ALBANIA ITALY ARGENTINA JAPAN AUSTRALIA REPUBLIC OF KOREA AUSTRIA LEBANON BELGIUM LUXEMBOURG BRAZIL MALI BULGARIA MEXICO BURMA MONACO BYELORUSSIAN SOVIET MOROCCO SOCIALIST REPUBLIC NETHERLANDS CAMBODIA NEW ZEALAND CANADA NICARAGUA CEYLON NORWAY CHILE PAKISTAN CHINA PARAGUAY COLOMBIA PERU CONGO (LEOPOLDVILLE) PHILIPPINES CUBA POLAND CZECHOSLOVAK SOCIALIST PORTUGAL REPUBLIC ROMANIA DENMARK SENEGAL DOMINICAN REPUBLIC SOUTH AFRICA ECUADOR SPAIN EL SALVADOR SUDAN ETHIOPIA SWEDEN FINLAND SWITZERLAND FRANCE THAILAND FEDERAL REPUBLIC TUNISIA OF GERMANY TURKEY GHANA UKRAINIAN SOVIET GREECE SOCIALIST REPUBLIC GUATEMALA UNION OF SOVIET HAITI SOCIALIST REPUBLICS HOLY SEE UNITED ARAB REPUBLIC HONDURAS UNITED KINGDOM OF GREAT HUNGARY BRITAIN AND NORTHERN ICELAND IRELAND INDIA UNITED STATES OF AMERICA INDONESIA VENEZUELA IRAN VIET-NAM IRAQ YUGOSLAVIA The Agency’s Statute was approved on 26 October 1956 at an international conference held at United Nations headquarters, New York, and the Agency came into being when the Statute entered into force on 29 July 1957. The first session of the General Conference was held in Vienna, Austria, the permanent seat of the Agency, in October, 1957. -
Liquid Scintillation Counting Techniques for the Determination of Some Alpha Emitting Actinides : a Review
2 LIQUID SCINTILLATION COUNTING TECHNIQUES FOR THE DETERMINATION OF SOME ALPHA EMITTING ACTINIDES : A REVIEW N.N.Mirashi, Keshav Chander and S.K.Aggarwal Fuel Chemistry Division, Bhabha Atomic Research Center, Mumbai - 400085. 1. INTRODUCTION Liquid scintillation process is based on the conversion of a part of the kinetic energy of alpha / beta / gamma radiation into photons. The photons are counted and related to the concentration of alpha/beta/gamma emitter. The principal use of liquid scintillation counting was the assay of low energy beta emitting nuclides. Alpha emitters could be counted by liquid scintillation counting was also known for long [1]. Alpha emitters, in spite of much lower scintillation yield compared to beta particles, are much more easily counted than beta particles, because alpha particles emit a line spectrum whereas beta spectrum is a continuum. The use of liquid scintillation counting is attractive because of its 100% counting efficiency and simplicity of sample preparation. Alpha particle assay by conventional plate counting methods is difficult because of chemical separation losses and/or self-absorption losses in the final sample may cause either non-reproducible results or create unacceptable errors. Several workers made applications of liquid scintillation counting technique to alpha counting in late 1950s and early 1960s [2-6]; still because of high background, interference from beta particles and very poor energy resolution for alpha energies liquid scintillation counting was not widespread for alpha counting. Horrocks [6] and Ihle et al [7] obtained a good degree of alpha energy resolution by liquid scintillation technique. This has led to identification and determination of mixture of alpha emitters. -
PRTM-1 (Rev. 1)
PRACTICAL RADIATION TECHNICAL MANUAL WORKPLACE MONITORING FOR RADIATION AND CONTAMINATION WORKPLACE MONITORING FOR RADIATION AND CONTAMINATION PRACTICAL RADIATION TECHNICAL MANUAL WORKPLACE MONITORING FOR RADIATION AND CONTAMINATION INTERNATIONAL ATOMIC ENERGY AGENCY VIENNA, 2004 WORKPLACE MONITORING FOR RADIATION AND CONTAMINATION IAEA, VIENNA, 2004 IAEA-PRTM-1 (Rev. 1) © IAEA, 2004 Permission to reproduce or translate the information in this publication may be obtained by writing to the International Atomic Energy Agency, Wagramer Strasse 5, P.O. Box 100, A-1400 Vienna, Austria. Printed by the IAEA in Vienna April 2004 FOREWORD Occupational exposure to ionizing radiation can occur in a range of industries, such as mining and milling; medical institutions; educational and research establishments; and nuclear fuel facilities. Adequate radiation protection of workers is essential for the safe and acceptable use of radiation, radioactive materials and nuclear energy. Guidance on meeting the requirements for occupational protection in accor- dance with the Basic Safety Standards for Protection against Ionizing Radiation and for the Safety of Radiation Sources (IAEA Safety Series No. 115) is provided in three interrelated Safety Guides (IAEA Safety Standards Series No. RS-G-1.1, 1.2 and 1.3) covering the general aspects of occupational radiation protection as well as the assessment of occupational exposure. These Safety Guides are in turn supplemented by Safety Reports providing practical information and technical details for a wide range of purposes, from methods for assessing intakes of radionuclides to optimization of radiation protection in the control of occupational exposure. Occupationally exposed workers need to have a basic awareness and under- standing of the risks posed by exposure to radiation and the measures for managing these risks.