Decontamination and Decommissioning of 61 Plutonium Gloveboxes in D-Wing, Building 212 Argonne National Laboratory - East: Final Project Report
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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 -
Dead Time and Count Loss Determination for Radiation Detection Systems in High Count Rate Applications
Scholars' Mine Doctoral Dissertations Student Theses and Dissertations Spring 2010 Dead time and count loss determination for radiation detection systems in high count rate applications Amol Patil Follow this and additional works at: https://scholarsmine.mst.edu/doctoral_dissertations Part of the Nuclear Engineering Commons Department: Nuclear Engineering and Radiation Science Recommended Citation Patil, Amol, "Dead time and count loss determination for radiation detection systems in high count rate applications" (2010). Doctoral Dissertations. 2148. https://scholarsmine.mst.edu/doctoral_dissertations/2148 This thesis is brought to you by Scholars' Mine, a service of the Missouri S&T Library and Learning Resources. This work is protected by U. S. Copyright Law. Unauthorized use including reproduction for redistribution requires the permission of the copyright holder. For more information, please contact [email protected]. DEAD TIME AND COUNT LOSS DETERMINATION FOR RADIATION DETECTION SYSTEMS IN HIGH COUNT RATE APPLICATIONS by AMOL PATIL A DISSERTATION Presented to the Faculty of the Graduate School of the MISSOURI UNIVERSITY OF SCIENCE AND TECHNOLOGY In Partial Fulfillment of the Requirements for the Degree DOCTOR OF PHILOSOPHY in NUCLEAR ENGINEERING 2010 Approved by Shoaib Usman, Advisor Arvind Kumar Gary E. Mueller Carlos H. Castano Bijaya J. Shrestha © 2010 AMOL PATIL All Rights Reserved iii PUBLICATION DISSERTATION OPTION This dissertation consists of the following two articles that have been, or will be submitted for publication as follows: Pages 4-40 are intended for submission to Journal of Radioanalytical and Nuclear Chemistry. Pages 41-62 have been published in Nuclear Technologies journal (February, 2009). iv ABSTRACT This research is focused on dead time and the subsequent count loss estimation in radiation detection systems. -
Dalton Transactions
Dalton Transactions View Article Online PAPER View Journal | View Issue The role of neutral Rh(PONOP)H, free NMe2H, boronium and ammonium salts in the dehydro- Cite this: Dalton Trans., 2019, 48, 14724 coupling of dimethylamine-borane using the 2 + cationic pincer [Rh(PONOP)(η -H2)] catalyst†‡ E. Anastasia K. Spearing-Ewyn,a Nicholas A. Beattie,b Annie L. Colebatch, a Antonio J. Martinez-Martinez, a Andrew Docker,a Timothy M. Boyd,a Gregg Baillie,b Rachel Reed,b Stuart A. Macgregor *b and Andrew S. Weller *a 1 F 3 The σ-amine-borane pincer complex [Rh(PONOP)(η -H3B·NMe3)][BAr 4][2, PONOP = κ -NC5H3-2,6- t 2 F (OP Bu2)2] is prepared by addition of H3B·NMe3 to the dihydrogen precursor [Rh(PONOP)(η -H2)][BAr 4], 1 F 1. In a similar way the related H3B·NMe2H complex [Rh(PONOP)(η -H3B·NMe2H)][BAr 4], 3, can be made in situ, but this undergoes dehydrocoupling to reform 1 and give the aminoborane dimer [H2BNMe2]2. Creative Commons Attribution 3.0 Unported Licence. NMR studies on this system reveal an intermediate neutral hydride forms, Rh(PONOP)H, 4, that has been prepared independently. 1 is a competent catalyst (2 mol%, ∼30 min) for the dehydrocoupling of H3B·Me2H. Kinetic, mechanistic and computational studies point to the role of NMe2H in both forming the neutral hydride, via deprotonation of a σ-amine-borane complex and formation of aminoborane, and Received 17th August 2019, closing the catalytic cycle by reprotonation of the hydride by the thus-formed dimethyl ammonium Accepted 3rd September 2019 + + [NMe2H2] . -
Nuclear Radiation 1. an Atom Contains Electrons, Protons and Neutrons
Nuclear Radiation 1. An atom contains electrons, protons and neutrons. Which of these particles a) are outside the nucleus b) are uncharged c) have a negative charge d) are nucleons e) are much lighter than the others? 2. Complete the table below. Name Symbol Charge What is it? Alpha particle β -1 Gamma ray An electromagnetic wave 3. How is an ionised material different from a material that is not ionised? National 5 Physics: Waves & Radiation 1 Absorption of Radiation 1. The figure below shows a Geiger tube used to detect radiation from a radioactive source. thick lead plate 0 4 2 5 start counter stop ON OFF reset Geiger tube radioactive source The following measurements were made using the apparatus above. Counts in 300 seconds Readings Average 1 No source present 102 94 110 2 Source present at fixed distance from tube a) No lead plate present 3466 3420 3410 b) Thick lead plate present 105 109 89 c) Aluminium sheet in place of the 1834 1787 1818 thick lead sheet a) Complete the table by calculating the average readings. b) Why are the readings on each line not the same? c) What can you say from the table about the effect on the radiation of: i. The lead plate? ii. The aluminium plate? d) Why is it possible to say from the readings that: i. gamma radiation is emitted by the source? ii. alpha and beta radiation might be emitted by the source? e) What further tests could you make using this arrangement to find out whether or not the source emits alpha radiation? National 5 Physics: Waves & Radiation 2 2. -
Elements of a Glovebox Glove Integrity Program
RESEARCH ARTICLE Elements of a Glovebox Glove Integrity Program Programmatic operations at the Los Alamos National Laboratory Plutonium Facility involve working with various amounts of plutonium and other highly toxic, alpha-emitting materials. The spread of radiological contamination on surfaces and airborne contamination and excursions of contaminants into the operator’s breathing zone are prevented through the use of a variety of gloveboxes. The glovebox gloves are the weakest part of this engineering control. As a matter of good business practice, a team of glovebox experts from Los Alamos National Laboratory has been assembled to proactively investigate processes and procedures that minimize unplanned openings in the glovebox gloves, i.e., breaches and failures. Working together, they have developed the key elements of an efficient Glovebox Glove Integrity Program (GGIP). In the following report, the consequences of a glove failure or breach are identified, the acceptable risk is clarified, and elements needed to implement an efficient GGIP are discussed. By Michael E. Cournoyer, INTRODUCTION Through an integrated approach, Julio M. Castro, controls have been developed and Michelle B. Lee, Plutonium requires a high degree of implemented that come from input Cindy M. Lawton, confinement and continuous control from glovebox workers, scientists, Young Ho Park, measures in nuclear research labora- health physicists, statisticians, and phy- Roy Lee, tories because of its extremely low sical therapists. Working together, they Stephen Schreiber permissible body burden.1 Methods have developed an efficient Glovebox and equipment must be designed Glove Integrity Program (GGIP). toward the ultimate accomplishment Recent accomplishes of this team have 2–5 Michael E. -
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. -
Copyright by Arthur Bryan Crawford 2004
Copyright by Arthur Bryan Crawford 2004 The Dissertation Committee for Arthur Bryan Crawford Certifies that this is the approved version of the following dissertation: Evaluation of the Impact of Non -Uniform Neutron Radiation Fields on the Do se Received by Glove Box Radiation Workers Committee: Steven Biegalski, Supervisor Sheldon Landsberger John Howell Ofodike Ezekoye Sukesh Aghara Evaluation of the Impact of Non -Uniform Neutron Radiation Fields on the Dose Received by Glove Box Radiation Workers by Arthur Bryan Crawford, B.S., M.S. Dissertation Presented to the Faculty of the Graduate School of The University of Texas at Austin in Partial Fulfillment of the Requirements for the Degree of Doctor of Philosophy The University of Texas at Austin December, 2004 Dedication I was born to goodly parents Harvey E. Crawford and Johnnie Lee Young Crawford Acknowledgements I would like to express my gratitude to Dr. Sheldon Landsberger for his vision in starting a distance learning program at the University of Texas at Austin and for his support and encouragement on this quest. I would like to thank my advisor, Dr. Steven Biegalski, for his support and encouragement even though the topic area was new to him. I would like to thank the members of my dissertation committee for finding the time to review this dissertation. To the staff of the Nuclear Engineering Teaching Laboratory I say thank you for your kindness and support during those brief times that I was on cam pus. A special thanks to my past and present group leaders, David Seidel, Eric McNamara, and Bill Eisele and my Division Leader, Lee McAtee, at Los Alamos National Laboratory, for their support in being allowed to use time and material resources at the Lab oratory and for financial support in the form of tuition reimbursement and travel expenses. -
General Glovebox Rules
Glovebox etiquette in the Lewis group Introduction: The gloveboxes are here to assist you in oxygen and water sensitive chemistry. The following guidelines are given to protect the box atmosphere and longevity and ultimately your chemistry and that of the whole group. If you feel that these guidelines impede your ability to do work, talk about it with the person in charge of the glovebox and they will help assist you in designing a set up that will work for you! Disregarding the guidelines compromises your chemistry as well as everyone elses. Available boxes: *Big Bird – Vac, purchased 2008. Drybox, Ar. Noyes 227B. Use for electrochemistry. O2 < 0.5 ppm *Snuffleupagus – Vac, older than time. Drybox, N2. Noyes 227B. Use for electrochemistry and storage. Absolutely no bad solvents/chemicals with the exception of CH3CN open for <5 minutes at a time. O2 < 1 ppm *Oscar the Grouch – Vac, older than time. Flushbox, N2. Noyes 227B. Alcohol OK. Electrochemistry, set-up, surface chemistry. O2 < 10 ppm *Elmo – Vac, purchased 2008. Drybox, N2. BI 032. Electrochemistry and chemical synthesis. O2 < 0.5 ppm *Count von Count – Mbraun, less old than time. Drybox, N2. BI 032. Don, Tony, electrochemistry and set up. O2 < 1 ppm *Cookie Monster – Vac, eh? As old as time?. Flushbox, N2. BI 023. Alcohol OK. Electrochemistry, set-up, surface chemistry. Connected to XPS. O2 < 10 ppm Note: Contact Box Czar before using a new box – even if you are trained on the old box. If nothing else, so they can keep track of who is using what and include you on important info for that box. -
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......................................................................................................................... -
Chapter 2 Radiation Safety Manual Revision 1 Principles of Radiation Safety 6/1/2018
The University of Georgia Chapter 2 Radiation Safety Manual Revision 1 Principles of Radiation Safety 6/1/2018 CHAPTER 2 PRINCIPLES OF RADIATION SAFETY 1.0 UNITS OF RADIATION DOSE 1.1 Historical Units In 1896, x-rays were discovered by Wilhelm Roentgen. The Roentgen is unit of measurement for the exposure of x-rays and gamma rays. It is defined as the electric charge freed by such radiation in a specified volume of air divided by the mass of that air. Radioactivity was discovered by Henri Becquerel. Radioactivity refers to the amount of radiation released when an element spontaneously emits energy as a result of the decay of its unstable atoms. The Becquerel is a unit used to measure radioactivity, and stands for 1 disintegration per second. The Curie is a unit of radioactivity equal to 3.7 X 1010 disintegrations per second and was first used, but being such a large unit was replaced by the Becquerel. The Curie is named for Pierre Curie, Marie Curie’s husband and co- discoverer of radium. After his accidental death, she continued their work. For some time, no one realized that radiation could cause harmful effects. It was recognized very soon that x-rays could be used in medical diagnosis, and early radiologists received large doses of radiation. Many of these radiologists later suffered severe injuries due to overexposure (radiation effects may appear years after exposure). The first unit of dose was the erythema dose. This was the amount of x-radiation which would barely cause reddening of the skin. It was not a very satisfactory unit of dose, but indicates the early recognition by some scientists that radiation exposure can be harmful and should be limited.