DOCSLIB.ORG

Lecture Notes

Total Page：16

File Type：pdf, Size：1020Kb

Download full-text PDF Read 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. ACCD: Advisory 4. SRC-RS: SRC for Radioactive 1. CRRE: Committee to Review Committee for Chemical Source Radiation Exposure Disposal 5. SRC-TRM: SRC for Transport of 2. SCCI: Standing Committee 2. BSMC: BARC Swachhta Radioactive Materials for Control, Monitoring Committee Abbreviations 6. SRC-TS: SRC for Temporary Instrumentation & 3. BTSC: BARC Traffic • Structures Computer based systems CEO: Conventional Engineering Operations Safety Committee • CFS: Conventional & Fire Safety 4. MHEC: Material Handling • DSRC: Design Safety Review Committee Equipment Committee Some of the Other Committees & Groups Responsible for Safety Regulation • SC: Safety Committee • Committees for conducting Emergency Exercises • SRC: Safety Review Committee • Plant Level and Local Safety Committees (PLSC & LSC) • ULSC: Unit Level Safety Committee • Radiological Safety Officers (RSO) • AG: Administrative Group • Regulatory Inspection Teams (RIT) • ESG: Engineering Service Group • Safety Coordinators • NRB: Nuclear Recycle Board • Task Forces and Working Groups constituted by various committees • NRG: Nuclear Recycle Group • Working Groups of DSRCs • PA: Particle Accelerators • Zonal Coordinators & Competent Persons of MHE • RDDG: Reactor Design & Development Group Fortieth Training Course on Safety and Regulatory Measures for BARC Facilities Lecture Notes February, 2020 BARC Safety Council Secretariat Table of Contents 1. REGULATORY FRAMEWORK FOR BARC FACILITIES ......................................... 1 2. RADIATION BASICS & NATURAL RADIATION ................................................... 11 3. RADIATION UNITS, DOSIMETRY AND DOSE LIMITS ........................................ 19 4. RADIATION DETECTION AND MEASUREMENT ................................................. 27 5. BIOLOGICAL EFFECTS OF RADIATION ................................................................. 39 6. INDUSTRIAL SAFETY ................................................................................................ 49 7. ELECTRICAL SAFETY................................................................................................ 55 8. ACCELERATOR SAFETY ........................................................................................... 63 9. OCCUPATIONAL HEALTH CARE ............................................................................ 71 10. FIRE PREVENTION, PROTECTION AND EXTINCTION........................................ 81 11. LASER SAFETY ........................................................................................................... 95 12. REGULATORY INSPECTION AND EVENT REPORTING ................................... 117 13. SAFETY CULTURE IN BARC FACILITIES ............................................................ 129 14. REGULATORY ASPECTS OF RADIOACTIVE WASTE MANAGEMENT .......... 139 15. TRANSPORT OF RADIOACTIVE MATERIAL ....................................................... 149 16. PREPAREDNESS AND RESPONSE TO NUCLEAR/ RADIOLOGICAL EMERGENCY ............................................................................................................. 163 REGULATORY FRAMEWORK FOR BARC FACILITIES 1. REGULATORY FRAMEWORK FOR BARC FACILITIES K. Jayarajan Chairman, BARC Safety Council [email protected] 1.0 Introduction Radiation and radioactive substances have wide applications, ranging from generation of power to use in medicine, industry, agriculture, and research. As high radiation is associated with high risk, India has accorded high priority for protecting the personnel, the public and the environment from nuclear and radiation hazards. Government of India has released many acts and Rules for this. Atomic Energy Act, 1962 provides the basic regulatory framework for all activities pertaining to atomic energy programme in India [1]. Radiation Protection Rules, 2004 [2] specifies the functions and responsibilities of the employer, the licensee, the workers and radiological safety officers. Atomic Energy (Factories) Rules, 1996 [3] enable statutory authorities to enforce regulatory control over inspectors, workplace hygiene, safe use of machinery, workers, protective equipment, etc. Atomic Energy Regulatory Board (AERB) and BARC Safety Council (BSC), constituted under the Atomic Energy Act, 1962, are the regulatory bodies in India, entrusted with the responsibility of protecting workers, public and the environment against harmful effects of ionizing radiation. While BSC regulates safety of BARC Facilities, AERB regulates nuclear and radiological facilities in public domain. AERB and BSC were constituted in the years 1983 in 2000 respectively. Wherever applicable, BSC complies with the principles of good safety management given in the relevant safety codes, guides and standards developed by AERB. It also complies with the acceptable limits of radiation exposure to the members of public prescribed by AERB. International organizations, such as International Atomic Energy Agency (IAEA) and International Commission on Radiological Protection (ICRP), develop standards, guidelines and recommendations, related to radiation and radioactive materials. National policies, legislation and regulations are developed from these standards, guidelines and recommendations. AERB and BSC follows IAEA Safety Fundamentals [4] for all activities related to radiation and radioactive materials. 2.0 Facilities Regulated by BSC 2.1 BARC Facilities and Projects All activities related to nuclear fuel cycle are performed in BARC. BARC has many plants, facilities and projects located in Mumbai, Tarapur, Kalpakkam, Vizag, Mysore, Hyderabad and many other parts of India. They include nuclear and radiological facilities, such as Research reactors, Particle accelerators, Radiological labs and Facilities for Fuel fabrication, Waste management, Radioisotope production, Food irradiation, Radiation medicine and Post irradiation examination. BARC also has many non-radiological facilities and upcoming projects. In BARC, R&D activities are carried out in many branches of science and engineering. Page | 1 REGULATORY FRAMEWORK FOR BARC FACILITIES 2.2 BARC Employees BARC has a large number of employees working in different parts of India. The number of employees of BARC at various places (as on February 1, 2020) is given below: Scientific Technical Administrative Auxiliary Total 1. Mumbai* 3243 3989 798 1975 10005 2. Tarapur 247 871 66 130 1314 3. Kalpakkam 387 871 76 54 1388 4. Mysore 164 544 48 128 884 5. Visakhapatnam 125 91 27 6 249 6. Other stations. 168 131 12 57 368 Total 4334 6497 1027 2350 14208 * Mumbai includes persons located at Anushaktinagar, Parel, Vashi & Kharghar In addition, BARC employs about 5500 casual workers and contract workers. 3.0 Safety Concerns in BARC The major safety concerns in BARC are nuclear and radiation hazards. Other hazards include, fire, chemical, electrical, laser, construction, biological, material-handling, accelerator and non- ionizing radiations. BARC carries out research and development in many advanced areas, where safety guides are not available. Therefore, safety guidelines for such areas need to be developed. 3.1 BARC Safety Council BARC has two regulatory bodies: BARC Safety Council (BSC) and BARC Safety Council for Specific Facilities (BSC-SF). BSC-SF regulates the safety of all specific facilities of BARC and radiological safety of all defence and other strategic facilities in India. BSC regulates safety of all other BARC facilities. Competent Authority : Director BARC BARC Safety Council BSC for Specific Facilities DSRCs (12) OPSRC CFSRC CRAASDRW PPSRC Safety Committees ULSCs (7) ULSCs (9) Expert Committees (12) Figure 1. BARC Safety Framework Page | 2 REGULATORY FRAMEWORK FOR BARC FACILITIES BSC consists of a Chairman, ten members and a member-secretary. BSC reports to Director, BARC. Elaborate multi-tiered system of safety
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]
  • An Annular Lithium-Drifted Germanium Detector for Studying Nuclear Reaction Gamma-Rays
    .. c .. I NASA CONTRACTOR REPORT 00 -m LOAN COPY: RETURN TO P AFWL (WLIL-2) I KIRTLAND AFB, N MEX e U 4 m 4 z AN ANNULAR LITHIUM-DRIFTED GERMANIUM DETECTORFOR STUDYING NUCLEAR REACTION GAMMA-RAYS Prepared by UNIVERSITY OF VIRGINIA Charlottesville, Va. fir NATIONAL AERONAUTICSAND SPACE ADMIRISTRATION WASHINGTON, D. c. SEPTEMBER 1968 TECH LIBRARY KAFB, NM / AN ANNULAR LITHIUM-DRIFTED GERMANIUM DETECTOR FOR STUDYING NUCLEAR REACTION GAMMA-RAYS /"-. .--L". By A-Le R. C:'i$RiJt,, and K. Ziock Distribution of this report is provided in the interest of informationexchange. Responsibility for the contents resides in the author or organization that prepared it. Pre red under Grant No. NsG-455 by, 7-VIRGINLA LL+"> Charlottesville, Va. for NATIONAL AERONAUTICS AND SPACE ADMINISTRATION Forsale by the Clearinghouse for Federal Scientific and Technical Information Springfield, Virginio 22151 - CFSTI price $3.00 " AN ANNULAR U:THIU"DRLFTEDGm DETECTOR FORSTUDYING NUCLEAR F3ACTION GAMMA-FLUS By A. J. Levy, R. C Ritter and K. Ziock Department of Physics University of Virginia Abstract A fabrication technique has been developed for truly annular Ge(Li) gamma. detectors.Featuring spask-cutting to preciselycontrol the un- damagedgermanium volume, the detector is capableof standard-geometry techniques such as are used with NaI detectors. In this report, background material relevant to the annular geometry is presented. An extremelyexplicit, detailed description of thecomplete fabricationprocedure is given,including special cutting, radiant diffusion, and drifting techniques developed here. Measured properties of several detectors are gresented, with the emphasis being on the usefulness of the detector for high energy gamma ray spectra. AN ANNUIAR LITHIUM-DRIFTED GERMANIUM DETECTOR FOR STUDYING NUCLEAR REACTION GAMMA-RAYS The Lithium-Drifted Germanium detector represents the mostadvanced stage in a systematicdevelopment of semiconductor materials anddevices made from them forthe purpose of radiation detection.
    [Show full text]