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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. -
3 Gamma-Ray Detectors
3 Gamma-Ray Detectors Hastings A Smith,Jr., and Marcia Lucas S.1 INTRODUCTION In order for a gamma ray to be detected, it must interact with matteu that interaction must be recorded. Fortunately, the electromagnetic nature of gamma-ray photons allows them to interact strongly with the charged electrons in the atoms of all matter. The key process by which a gamma ray is detected is ionization, where it gives up part or all of its energy to an electron. The ionized electrons collide with other atoms and liberate many more electrons. The liberated charge is collected, either directly (as with a proportional counter or a solid-state semiconductor detector) or indirectly (as with a scintillation detector), in order to register the presence of the gamma ray and measure its energy. The final result is an electrical pulse whose voltage is proportional to the energy deposited in the detecting medhtm. In this chapter, we will present some general information on types of’ gamma-ray detectors that are used in nondestructive assay (NDA) of nuclear materials. The elec- tronic instrumentation associated with gamma-ray detection is discussed in Chapter 4. More in-depth treatments of the design and operation of gamma-ray detectors can be found in Refs. 1 and 2. 3.2 TYPES OF DETECTORS Many different detectors have been used to register the gamma ray and its eneqgy. In NDA, it is usually necessary to measure not only the amount of radiation emanating from a sample but also its energy spectrum. Thus, the detectors of most use in NDA applications are those whose signal outputs are proportional to the energy deposited by the gamma ray in the sensitive volume of the detector. -
1. Gamma-Ray Detectors for Nondestructive Analysis P
1. GAMMA-RAY DETECTORS FOR NONDESTRUCTIVE ANALYSIS P. A. Russo and D. T. Vo I. INTRODUCTION AND OVERVIEW Gamma rays are used for nondestructive quantitative analysis of nuclear material. Knowledge of both the energy of the gamma ray and its rate of emission from the unknown mass of nuclear material is required to interpret most measurements of nuclear material quantities. Therefore, detection of gamma rays for nondestructive analysis of nuclear materials requires both spectroscopy capability and knowledge of absolute specific detector response. Some techniques nondestructively quantify attributes other than nuclear material mass, but all rely on the ability to distinguish elements or isotopes and measure the relative or absolute yields of their corresponding radiation signatures. All require spectroscopy and most require high resolution. Therefore, detection of gamma rays for quantitative nondestructive analysis (NDA) of the mass or of other attributes of nuclear materials requires spectroscopy. A previous book on gamma-ray detectors for NDA1 provided generic descriptions of three detector categories: inorganic scintillation detectors, semiconductor detectors, and gas-filled detectors. This report described relevant detector properties, corresponding spectral characteristics, and guidelines for choosing detectors for NDA. The current report focuses on significant new advances in detector technology in these categories. Emphasis here is given to those detectors that have been developed at least to the stage of commercial prototypes. The type of NDA application – fixed installation in a count room, portable measurements, or fixed installation in a processing line or other active facility (storage, shipping/receiving, etc.) – influences the choice of an appropriate detector. Some prototype gamma-ray detection techniques applied to new NDA approaches may revolutionize how nuclear materials are quantified in the future. -
DRC-2016-012921.Pdf
CLN-SRT-011 R1.0 Page 2 of 33 Introduction ................................................................................................................................ 3 Sources of Radiation .................................................................................................................. 3 Radiation: Particle vs Electromagnetic ....................................................................................... 5 Ionizing and non- ionizing radiation ............................................................................................ 8 Radioactive Decay ....................................................................................................................10 Interaction of Radiation with Matter ...........................................................................................15 Radiation Detection and Measurement .....................................................................................17 Biological Effects of Radiation ...................................................................................................18 Radiation quantities and units ...................................................................................................18 Biological effects .......................................................................................................................20 Effects of Radiation by Biological Organization .........................................................................20 Mechanisms of biological damage ............................................................................................21 -
Portable Front-End Readout System for Radiation Detection
Portable Front-End Readout System for Radiation Detection by Maris Tali THESIS for the degree of MASTER OF SCIENCE (Master in Electronics) Faculty of Mathematics and Natural Sciences University of Oslo June 2015 Det matematisk- naturvitenskapelige fakultet Universitetet i Oslo Portable Front-End Readout System for Radiation Detection Maris Tali Portable Front-End Readout System for Radiation Detection Maris Tali Portable Front-End Readout System for Radiation Detection Acknowledgements First of all, I would like to thank my advisor, Ketil Røed, for giving me the opportunity to write my master thesis on such an interesting and challenging subject as radiation instrumentation and measurement. I would also like to thank him for his insight and guidance during my master thesis and for the exciting opportunities during my studies to work in a real experimental environment. I would also like to thank the Electronic Laboratory of the University of Oslo, specif- ically Halvor Strøm, David Bang and Stein Nielsen who all gave me valuable advice and assistance and without whom this master thesis could not have been finished. Lastly, I would like to thank the co-designer of the system whom I worked together with during my master thesis, Eino J. Oltedal. It is customary to write that half of ones master thesis belongs to ones partner. However, this is actually the case in this instance so I guess 2/3 of my master thesis is yours and I definitely could not have done this without you. So, thank you very much! Oslo, June 2015 Maris Tali I Maris Tali Portable Front-End Readout System for Radiation Detection Contents Acknowledgments I Glossary VI List of Figures X List of Tables X Abstract XI 1 Introduction 1 1.1 Background and motivation . -
Optimization of a Gas Flow Proportional Counter for Alpha Decay
Optimization of a gas flow proportional counter for alpha decay measurements Elena Ceballos Romero Master Thesis Institut f¨urKernphysik Mathematisch-Naturwissenschaftliche Fakult¨at Westf¨alische Wilhelms-Universit¨atM¨unster Prof. Dr. Alfons Khoukaz October 2012 III I am among those who think that science has great beauty. A scientist in his laboratory is not only a technician: he is also a child placed before natural phenomena which impress him like a fairy tale. We should not allow it to be believed that all scientific progress can be reduced to mechanisms, machines, gearings, even though such machinery has its own beauty. -Marie Curie A magdalena, por ponerme en este camino. A mis padres, por siempre acompa~narmeen ´el. IV V I certify that I have independently written this thesis and no other sources than the mentioned ones have been used. Referent: Prof. Dr. Alfons Khoukaz Correferent: Dr. Mar´ıaVilla Alfageme VI Contents 1. Introduction 1 2. Introduction to natural radiations 5 2.1. Radioactivity . .5 2.1.1. Decay laws . .5 2.1.2. Activity . .7 2.2. Decays . .7 2.2.1. Alpha decay . .7 2.2.2. Beta decay . .9 2.2.3. Gamma decay . 11 3. Theoretical background: Gas-filled detectors 13 3.1. General properties . 13 3.1.1. Number of ion pairs formed . 14 3.1.2. Behaviour of charged particles in gases . 14 3.1.3. Operational modes of gas detectors . 15 3.2. Proportional counters: gas multiplication effect . 17 3.3. Gas flow detectors . 18 4. Experimental set-up 21 4.1. Detector . 21 4.1.1. -
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. -
Semiconductor Detectors Silvia Masciocchi GSI Darmstadt and University of Heidelberg
Semiconductor detectors Silvia Masciocchi GSI Darmstadt and University of Heidelberg 39th Heidelberg Physics Graduate Days, HGSFP Heidelberg October 10, 2017 Semiconductor detector: basics IONIZATION as in gas detectors → Now in semiconductors = solid materials with crystalline structure (Si, Ge, GaAs) → electron-hole pairs (instead of electron-ion) + use microchip technology: structures with few micrometer precision can be produced at low cost. Read-out electronics can be directly bonded to the detectors + only a few eV per electron-hole pair → 10 times more charge produced (wrt gas) → better energy resolution + high density compared to gases → need only thin layers (greater stopping power) – apart from silicon, the detectors need to be cooled (cryogenics) – crystal lattices → radiation damage [email protected] Semiconductor detectors, October 11, 2017 2 Applications Main applications: ● γ spectroscopy with high energy resolution ● Energy measurement of charged particles (few MeV) and particle identification (PID) via dE/dx (multiple layers needed) ● Very high spatial resolution for tracking and vertexing A few dates: 1930s – very first crystal detectors 1950s – first serious developments of particle detectors 1960s – energy measurement devices in commerce [email protected] Semiconductor detectors, October 11, 2017 3 Semiconductor detectors: outline ● Principle of operation of semiconductor detectors ● Properties of semiconductors (band structure) ● Intrinsic material ● Extrinsic (doped) semiconductors ● p-n junction ● Signal generation ● Energy measurement with semiconductor detectors ● Position measurement with semiconductor detectors ● Radiation damage [email protected] Semiconductor detectors, October 11, 2017 4 Principle of operation ● Detector operates as a solid state ionization chamber ● Charged particles create electron-hole pairs ● Place the crystal between two electrodes that set up an electric field → charge carriers drift and induce a signal ● Less than 1/3 of energy deposited goes into ionization. -
Radiation Fields Using a Tepc*
XA00XC014 EUROPEAN LABORATORY FOR PARTICLE PHYSICS CERN/TIS-RP/95-14/CF A STUDY OF BUILD-UP EFFECTS IN HIGH-ENERGY RADIATION FIELDS USING A TEPC* M. Hofert1), A. Aroua2), A. V. Sannikov3) and G. R. Stevenson1) !) CERN, European Laboratory for Particle Physics, CH 1211 Geneva 23, Switzerland 2) IAR, Institute for Applied Radiophysics, CH 1015 Lausanne, Switzerland 3) IHEP, Institute for High-Energy Physics, RU 142284 Protvino, Russia * Supported by EU Research Contract FI3P-CT92-0026 Abstract A dose of 2 mSv close to the body surface of a pregnant woman is considered by ICRP to assure a dose limit of 1 mSv to the foetus. Such an assumption depends on the energy spectrum and composition of the external radiation field and it was tested in radiation fields containing high-energy particles similar to those found around high-energy particle accelerators and in air-craft. Measurements of dose and dose equivalent were performed as a function of wall thickness using a tissue-equivalent proportional counter (TEPC) in radiation fields at the CERN-EU Reference Radiation Facility. Results are presented both with respect to integral quantities and event size spectra. The decrease in dose and dose equivalent at a depth equivalent to that of the foetus was typically 10% in a high-energy stray radiation field and in the case of Pu- Be source neutrons amounted to only 30%. It is concluded that it would be prudent under such exposure conditions to limit the dose of a pregnant woman to 1 mSv in order to assure that the dose to the foetus remains below the same limit. -
Internal and External Exposure Exposure Routes 2.1
Exposure Routes Internal and External Exposure Exposure Routes 2.1 External exposure Internal exposure Body surface From outer space contamination and the sun Inhalation Suspended matters Food and drink consumption From a radiation Lungs generator Radio‐ pharmaceuticals Wound Buildings Ground Radiation coming from outside the body Radiation emitted within the body Radioactive The body is equally exposed to radiation in both cases. materials "Radiation exposure" refers to the situation where the body is in the presence of radiation. There are two types of radiation exposure, "internal exposure" and "external exposure." External exposure means to receive radiation that comes from radioactive materials existing on the ground, suspended in the air, or attached to clothes or the surface of the body (p.25 of Vol. 1, "External Exposure and Skin"). Conversely, internal exposure is caused (i) when a person has a meal and takes in radioactive materials in the food or drink (ingestion); (ii) when a person breathes in radioactive materials in the air (inhalation); (iii) when radioactive materials are absorbed through the skin (percutaneous absorption); (iv) when radioactive materials enter the body from a wound (wound contamination); and (v) when radiopharmaceuticals containing radioactive materials are administered for the purpose of medical treatment. Once radioactive materials enter the body, the body will continue to be exposed to radiation until the radioactive materials are excreted in the urine or feces (biological half-life) or as the radioactivity weakens over time (p.26 of Vol. 1, "Internal Exposure"). The difference between internal exposure and external exposure lies in whether the source that emits radiation is inside or outside the body. -
A Direct Search for Dark Matter with the Majorana Demonstrator
A DIRECT SEARCH FOR DARK MATTER WITH THE MAJORANA DEMONSTRATOR Kristopher Reidar Vorren A dissertation submitted to the faculty at the University of North Carolina at Chapel Hill in partial fulfillment of the requirements for the degree of Doctor of Philosophy in the Department of Physics. Chapel Hill 2017 Approved by: Reyco Henning Chris Clemens Jonathan Engel Christian Iliadis John F. Wilkerson c 2017 Kristopher Reidar Vorren ALL RIGHTS RESERVED ii ABSTRACT Kristopher Reidar Vorren: A Direct Search for Dark Matter with the Majorana Demonstrator (Under the direction of Reyco Henning) The Majorana Demonstrator is a neutrinoless double-beta decay experiment cur- rently operating 4850 ft underground in the Sanford Underground Research Facility in Lead, SD. Sub-keV thresholds and excellent low-energy resolution are features of the p-type point- contact high-purity germanium detectors deployed by Majorana, making them ideal for use in direct dark matter searches when combined with Majorana's ultra-low backgrounds. An analysis of data from a 2015 commissioning run of the Demonstrator with 478 kg d of exposure was performed to search for mono-energetic lines in the detectors' energy-spectrum from bosonic dark matter absorption. No dark matter signature was found in the 5-100 keV range, and upper limits were placed on dark bosonic pseudoscalar and vector-electric cou- plings. The same analysis produced null results and upper limits for three additional rare- event searches: Pauli-Exclusion Principle violating decay, solar axions, and electron decay. Improvements made to Majorana since commissioning will result in increased sensitivity to rare-event searches in future analyses. -
Semiconductor Detectors Part 1
1 Lectures on Detector Techniques Stanford Linear Accelerator Center September 1998 – February, 1999 Semiconductor Detectors Part 1 Helmuth Spieler Physics Division Lawrence Berkeley National Laboratory for more details see UC Berkeley Physics 198 course notes at http://www-physics.lbl.gov/~spieler Semiconductor Detectors Helmuth Spieler SLUO Lectures on Detector Techniques, October 23, 1998 LBNL 2 1. Principles Important excitations when radiation is absorbed in solids 1. atomic electrons ⇒ mobile charge carriers ⇒ lattice excitations (phonons) 2. elastic scattering on nuclei Recoil energy < order 10 eV ⇒ ionization ⇒ lattice excitations (phonons) at higher recoil energies ⇒ radiation damage (displacement of from lattice sites) Semiconductor Detectors Helmuth Spieler SLUO Lectures on Detector Techniques, October 23, 1998 LBNL 3 Most Semiconductor Detectors are Ionization Chambers Detection volume with electric field Energy deposited → positive and negative charge pairs Charges move in field → current in external circuit (continuity equation) Semiconductor Detectors Helmuth Spieler SLUO Lectures on Detector Techniques, October 23, 1998 LBNL 4 Ionization chambers can be made with any medium that allows charge collection to a pair of electrodes. Medium can be gas liquid solid Crude comparison of relevant properties gas liquid solid density low moderate high atomic number Z low moderate moderate ionization energy εi moderate moderate low signal speed moderate moderate fast Desirable properties: low ionization energy ⇒ 1. increased charge