DOCSLIB.ORG

Determining Dose Rate with a Semiconductor Detector - Monte Carlo Calculations of the Detector Response

Total Page：16

File Type：pdf, Size：1020Kb

Download full-text PDF Read full-text
Determining Dose Rate with a Semiconductor Detector - Monte Carlo Calculations of the Detector Response SE9900106 FOA-R--99-01035-861 --SE February 1999 FOA ISSN 1104-9154 DEFENCE RESEARCH Technical Report ESTABLISHMENT Charlotte Nordenfors Determining dose rate with a semiconductor detector - Monte Carlo calculations of the detector response Division of NBC Defence SE-901 82 UMEA DEFENCE RESEARCH ESTABLISHMENT FOA-R--99-01035-861-SE Division of NBC Defence February 1999 SE-901 82 UMEA ISSN 1104-9154 SWEDEN Charlotte Nordenfors Determining dose rate with a semiconductor detector - Monte Carlo calculations of the detector response Distribution: SkyddS, SSI Issuing organization Document ref. No., ISRN Defence Research Establishment FO A-R--99-01035-861 -SE Division of NBC Defence Date of issue Project No. SE-901 82 UMEA February 1999 E415 SWEDEN Project name (abbrev. if necessary) Author(s) Initiator or sponsoring organization FOA Charlotte Nordenfors Project manager Torbjorn Nylen Scientifically and technically responsible Thomas Ulvsand Document title Determining dose rate with a semiconductor detector - Monte Carlo calculations of the detector response Abstract To determine dose rate in a gamma radiation field, based on measurements with a semiconductor detector, it is necessary to know how the detector effects the field. This work aims to describe this effect with Monte Carlo simulations and calculations, that is to identify the detector response function. This is done for a germanium gamma detector owned by the department of Nuclear Weapon Issues and Radiaton Science at the Swedish National Defence Research Establishment in Umea. The detector is normally used in the in-situ measurements that is carried out regularly at the department. After the response function is determined it is used to reconstruct a spectrum from an in-situ measurement, a so called unfolding. This is done to be able to calculate fluence rate and dose rate directly from a measured (and unfolded) spectrum. The Monte Carlo code used in this work is EGS4 (Electron Gamma Shower, version 4) developed mainly at Stanford Linear Accelerator Center. It is a widely used code package to simulate particle transport with The results of this work indicates that the method could be used as-is since the accuracy of this method compares to other methods already in use to measure dose rate. Bearing in mind that this method provides the nuclide specific dose it is useful, in radiation protection, since knowing what the relations between different nuclides are and how they change is very important when estimating the risks. Keywords Dose rate,semiconductor detector, Monte Carlo methods, gamma ray spectromety, EGS4 Further bibliographic information Language English ISSN 1104-9154 ISBN Pages 77 p. Price Ace. to pricelist Distributor (if not issuing organization) Dokumentets utgivare Dokumentbeteckning, ISRN Försvarets forskningsanstalt FOA-R-99-01035-861--SE Avdelningen för NBC-skydd Dokumentets datum Uppdragsnummer 901 82 UMEÅ Februari 1999 E415 Projektnamn (ev förkortat) Upphovsman(män) Uppdragsgivare FOA Charlotte Nordenfors Projektansvarig Torbjörn Nylén Fackansvarig Thomas Ulvsand Dokumentets titel i översättning Dosratsbestämning med halvledar-detektor - Monte Carlo beräkning av detektor respons Sammanfattning För att bestämma dosrat i ett gammastrålfält baserat på mätningar med en halvledardetektor måste man känna till hur detektorn påverkar strålfältet. Målet med det här arbetet är att beskriva denna påverkan med hjälp av Monte Carlo simulering och beräkning d.v.s. ta fram detektorns responsfunktion. Detta görs för en germanium gammadetektor som ägs av institutionen för kärnvapenfrågor och strålningsvetenskap vid Försvarets forskningsanstalt i Umeå. Detektorn används normalt vid de in-situ mätningar som görs regelbundet vid institutionen. Då responsfunktionen är känd används den för att rekonstruera ett uppmätt spektrum. När detta är gjort kan fluensrat och dosrat beräknas direkt från det uppmätta (och rekonstruerade) spektrumet. Monte Carlo-koden som används i arbetet är EGS4 (Electron Gamma Shower, version 4) som utvecklats huvudsakligen vid Stanford Linear Accelerator Center. Det är ett ofta använt programpaket för simulering av partikeltransport. Resultaten pekar på att metoden kan användas som den är eftersom noggrannheten kan jämföras med metoder som redan används för att mäta dosrat. Med tanke på att denna metod ger den isotopspecifika dosen är den användbar, i strålskyddssammanhang, eftersom det är viktigt att känna till relationerna mellan olika isotoper och hur dessa ändras då riskuppskattningar görs. Nyckelord Dosrat, halvledardetektor, Monte Carlo-metoder, EGS4, gamma spektrometri Övriga bibliografiska uppgifter Språk Engelska ISSN 1104-9154 ISBN Omfång 77 s. Pris Enligt prislista Distributör (om annan än ovan) V.1.1 Contents Preface vii 1 Introduction 1 2 Gamma-ray spectrometry 3 2.1 Photon interactions 3 2.1.1 Photoelectric absorption 3 2.1.2 Compton scattering 4 2.1.3 Pair production 5 2.2 Contributions to the detector response .... 6 2.2.1 The very large detector 7 2.2.2 The very small detector 7 2.2.3 The real detector 8 2.2.4 Summing up the detector response . 9 2.3 Semiconductor detectors 10 2.3.1 The portable high purity germanium de- tector 11 3 The theory of unfolding the response function 15 3.1 The unfolding 15 3.2 How to find the inherent response function . 17 4 EGS4 - The Monte Carlo package 19 4.1 A summary of capabilities and features .... 19 4.2 How to use EGS4 20 4.3 PEGS4 - data preparation 21 4.4 DOSRZ - a User Code 22 5 Calculations 25 5.1 The detector model 25 5.2 Input parameters 30 vi CONTENTS 5.3 The output 32 6 Results of the unfolding 35 6.1 The procedure 35 6.2 Comparison with point source measurements . 35 6.3 In-situ measurements and angular dependence 36 6.4 Discussion 37 7 Conclusions 39 7.1 Further developments 39 References 40 A Detector data 43 B Input and output from EGS4 49 B.I .egs4inp 49 B.2 .egs41st 53 B.3 .egs4eff 58 C Calculations 61 C.I DOSRZ - the regions of the detector model . 61 C.2 Empirical values of the efficiency 62 D Unfolding 63 D.I Point source 63 E Wave programs 65 E.I The point source unfolding 65 E.2 The in-situ unfolding 66 E.3 Fixing the vector with the measured spectrum 68 E.4 Making the matrix 69 Preface This work is a master thesis within the Physical Engineering program at Umea University and is done at the department of nuclear weapon issues and radiation science within the Na- tional Defence Research Establishment (FOA) in Umea. Su- pervisor is Thomas Ulvsand together with Goran Agren and Kenneth Lidstrom. The examinator is Lennart Olofsson, de- partment of radiation physics at Umea University. The au- thor likes to thank all of the above for the help with this work and Hans Holmstrom for patience and help with UNIX and computer related questions. vn Chapter 1 Introduction There is a need for efficient methods to determine radioactiv- ity in the environment e.g. after nuclear accidents or for large area surveys. One such method is gamma-ray spectrometry performed in the contaminated environment, so called in-situ spectrometry. The measurements are done near the radioac- tive source and usually one meter above the ground. This kind of spectrometry is used to determine the activity levels in the ground or in the air. The method of in-situ gamma-ray spectrometry has been widely used after the reactor accidents at Three Mile Island (USA, 1979) and Chernobyl (USSR, 1986). Especially the latter convinced many of the necessity for quick and reliable methods to determine radionuclide contamination. Perhaps even more important for the spread of the method is the de- velopment of portable high purity germanium detectors that are easy to handle and available at a reasonable cost. A de- scription of these detectors is found in section 2.3 below. To judge the biological effect the radiation has on for ex- ample humans it is of interest to find the radionuclide specific as opposed to the total dose rate in an area. So in some ap- plications of radiation protection it would desirable to mea- sure the radionuclide specific dose rate distribution directly by in-situ gamma-ray spectrometry. The result of a measure- ment with a germanium detector is a pulse-height distribu- tion which represents the spectral distribution of the energy deposition events in its active volume. A substantial fraction of these events corresponds to photons that only deposited a fraction of their incoming energy. Also, the detector dis- 1 CHAPTER 1. INTRODUCTION turbs the measurements due to interaction between the in- coming photons and the detector housing and cooling system. This leads to a superposition of counts coming from full en- ergy deposition of radiation scattered in the environment with counts corresponding to partial energy deposition events (sec- tion 2.2). All this has to be taken in to account in order to obtain the photon fiuence rate spectrum and consequently the dose rate spectrum. By applying an unfolding procedure to the measured pulse- height distribution, in which the partial energy deposition events are subtracted, a conversion to fiuence is made. This unfolding procedure requires an accurate and detailed knowl- edge of the response of the detector to monoenergetic photons of energies in the range of the spectrum. The theoretical back- ground to the unfolding and how the response function can be calculated using Monte Carlo methods is described in chapter 3. The goal of the present work is to determine the response function, for one of the two germanium detectors in use at department 41, and to unfold a measured spectrum. One widely used general purpose Monte Carlo package is EGS4, (Electron Gamma Shower version 4), and it is de- scribed in chapter 4 together with the usercode DOSRZ that is used in this work to sample the pulse-height distribution in a model of the detector.
Load more

Recommended publications
  • 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.
    [Show full text]
  • 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.
    [Show full text]
  • 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
    [Show full text]
  • 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 .
    [Show full text]
  • 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.
    [Show full text]
  • 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.
    [Show full text]
  • 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.
    [Show full text]
  • 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
    [Show full text]
  • Semiconductor Detectors - an Introduction
    Lawrence Berkeley National Laboratory Lawrence Berkeley National Laboratory Title SEMICONDUCTOR DETECTORS - AN INTRODUCTION Permalink https://escholarship.org/uc/item/8vn2v63q Author Goulding, F.S. Publication Date 1978-04-01 eScholarship.org Powered by the California Digital Library University of California NOTICE 1 Tkk itfon Ml ptepued w an account of work •pouored by (he United Sum Government. Nrtthei the United Sutei not ft* United SUM Deptflment of SEMICONDUCTOR DETECTORS - AN INTRODUCTION* Eneigy, nor My of theft emptoytti, nor my of iheti LBL-7282 eantnclon, nibcoatricfon, o.- their employee], tukei •ny wtmnty, tiprtn or (replied, or utiana any lefaJ F. S. Goulding Ikbfliiy oi raponrtffity foi <heKcuncy,cttii|4ctene(( Of lacfulncM o( any information, apparatus, product or Lawrence Berkeley Laboratory piODcm dfcetaed, o( reprMenb thil !u tnr would not University of California infrinfc primely owned dtfiw. Berkeley, California 94720 I. History (i) To first order charge collection in a detector only occurs from regions where an electric Semiconductor detectors appeared on the scene' of field exists. Diffusion does occur from Nuclear Physics in about I960, although McKay of Bell field-free regions, but it is slow and its Laboratories had demonstrated the detection of alpha effects are usually undesirable. In junction particles by semiconductor diodes several years or surface-barrier (sometimes called Schottky- earlier. The earliest work, just prior to 1960, barrler) detectors, this means that the "de­ focused on relatively thin surface barrier germanium pletion layer" is the sensitive region of a detectors, used to detect short-range particles. detector. These detectors, used at low temperature to reduce leakage current, demonstrated the potential of semi­ (11) The thickness of a depletion layer 1 a semi­ conductor detectors to realize energy resolutions conductor diode is proportional to substantially better than the ionization (gas) chambers used earlier.
    [Show full text]
  • Semiconductor Pixel Detectors for Characterisation of Therapeutic Proton Beams
    AGH University of Science and Technology Faculty of Physics and Applied Computer Science Engineering thesis Semiconductor pixel detectors for characterisation of therapeutic proton beams Paulina Stasica Medical Physics Supervisor: dr inż. Jan Gajewski Proton Radiotherapy Group The Henryk Niewodniczanski Institute of Nuclear Physics Polish Academy of Sciences Kraków, January 2020 dr inż. Jan Gajewski Instytut Fizyki Jądrowej PAN Merytoryczna ocena pracy przez opiekuna: Pani Paulina Stasica przygotowała pracę inżynierską, która jest elementem projektu ba- dawczego Fundacji na Rzecz Nauki Polskiej zatytułowanego „Ocena niepewności zasięgu efektu biologicznego w celu poprawy skuteczności radioterapii protonowej w Centrum Cyklotronowym Bronowic”, realizowanego w Instytucie Fizyki Jądrowej PAN w Krakowie. Praca inżynierska podzielona jest na trzy części: wstęp teoretyczny, część opisującą zasto- sowane metody eksperymentalne oraz wyniki i dyskusję pomiarów i symulacji Monte Carlo. Pracę kończy rozdział z wnioskami. We wstępie teoretycznym zostały opisane formy oddziaływań wysokoenergetycznych pro- tonów z materią oraz podstawy radioterapii protonowej, w tym rola względnej wydajności biologicznej i jej zależność od liniowego przekazu energii. W kolejnym rozdziale opisano zastosowanie półprzewodnikowych detektorów pikselowych typu Timepix MiniPIX do pomiaru depozycji energii w mieszanych polach promieniowania indukowanych przez wiązkę protonową. Opisano dwa typy eksperymentów przeprowadzonych przez Autorkę pracy, mających na celu zbadanie zdolności
    [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]
  • Lecture Notes
    Fortieth Training Course on Safety and Regulatory Measures for BARC Facilities February 26-29, 2020 Anushaktinagar, Mumbai Lecture Notes BARC SAFETY COUNCIL SECRETARIAT BARC SAFETY FRAMEWORK Competent Authority Director, BARC BARC Safety Council BARC Safety Council -Specific Facilities Safety Committees for (BSC) (BSC-SF) Specific Facilities DSRCs & SRCs PPSRC OPSRC CFSRC CRAASDRW 1. DSRC-AP: Accelerator Projects Physical Protection System Operating Plants Safety Conventional and Fire Committee to Review Application for 2. DSRC -CFB: Common Facility Building Review Committee Review Committee Safety Review Committee Authorisation of Safe Disposal of 3. DSRC-CFV: Conventional Facilities, Vizag Radioactive Waste 4. DSRC-HFRR: High Flux Research ULSCs Reactor 1. MOSC: Metallurgical ULSCs 5. DSRC-IPF: I-131 Processing Facility All ULSCS Operations SC 1. ULSC-AG 6. DSRC-NRFN: Nuclear Reactor Facility- 2. ULSC-RO Radiological 2. ULSC-CEO All ULSCS North Site Operations) 3. ULSC-CFS Kalpakkam 7. DSRC -NRB: Nuclear Recycle Board 3. ULSC-RR (Research 4. ULSC-CFS Tarapur 8. DSRC-NRG: Nuclear Recycle Group Reactors) 5. ULSC-CFS Vizag Expert Committees 9. DSRC -RMRC: Radiation Medicine 4. ULSC-NRB-Kalpakkam 6. ULSC-ESG 1. ACOH: Advisory Committee on Research Centre, Kolkata 5. ULSC-NRB-Tarapur 7. ULSC-Med: Medical Occupational Health 10. DSRC -SNRF: Safe-guarded Nuclear 6. ULSC-NRG 8. ULSC-ML: Mod Lab 2. CRLRSO: Committee to Recycle Facility 7. ULSC-PA (Particle 9. ULSC-RDDG Recommend Licensing of 11. SRC-LNTC: Live Nuclear Training Accelerators) Radiological Safety Officers Complex, CME, Pune 3. DAC: Standing Committee on 12. SRC- NC: New Constructions Expert Committees Dose Apportionment Expert Committees 1.
    [Show full text]