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Lecture 6: Spectroscopy and Photochemistry II
Lecture 6: Spectroscopy and Photochemistry II Required Reading: FP Chapter 3 Suggested Reading: SP Chapter 3 Atmospheric Chemistry CHEM-5151 / ATOC-5151 Spring 2005 Prof. Jose-Luis Jimenez Outline of Lecture • The Sun as a radiation source • Attenuation from the atmosphere – Scattering by gases & aerosols – Absorption by gases • Beer-Lamber law • Atmospheric photochemistry – Calculation of photolysis rates – Radiation fluxes – Radiation models 1 Reminder of EM Spectrum Blackbody Radiation Linear Scale Log Scale From R.P. Turco, Earth Under Siege: From Air Pollution to Global Change, Oxford UP, 2002. 2 Solar & Earth Radiation Spectra • Sun is a radiation source with an effective blackbody temperature of about 5800 K • Earth receives circa 1368 W/m2 of energy from solar radiation From Turco From S. Nidkorodov • Question: are relative vertical scales ok in right plot? Solar Radiation Spectrum II From F-P&P •Solar spectrum is strongly modulated by atmospheric scattering and absorption From Turco 3 Solar Radiation Spectrum III UV Photon Energy ↑ C B A From Turco Solar Radiation Spectrum IV • Solar spectrum is strongly O3 modulated by atmospheric absorptions O 2 • Remember that UV photons have most energy –O2 absorbs extreme UV in mesosphere; O3 absorbs most UV in stratosphere – Chemistry of those regions partially driven by those absorptions – Only light with λ>290 nm penetrates into the lower troposphere – Biomolecules have same bonds (e.g. C-H), bonds can break with UV absorption => damage to life • Importance of protection From F-P&P provided by O3 layer 4 Solar Radiation Spectrum vs. altitude From F-P&P • Very high energy photons are depleted high up in the atmosphere • Some photochemistry is possible in stratosphere but not in troposphere • Only λ > 290 nm in trop. -
VISCOSITY of a GAS -Dr S P Singh Department of Chemistry, a N College, Patna
Lecture Note on VISCOSITY OF A GAS -Dr S P Singh Department of Chemistry, A N College, Patna A sketchy summary of the main points Viscosity of gases, relation between mean free path and coefficient of viscosity, temperature and pressure dependence of viscosity, calculation of collision diameter from the coefficient of viscosity Viscosity is the property of a fluid which implies resistance to flow. Viscosity arises from jump of molecules from one layer to another in case of a gas. There is a transfer of momentum of molecules from faster layer to slower layer or vice-versa. Let us consider a gas having laminar flow over a horizontal surface OX with a velocity smaller than the thermal velocity of the molecule. The velocity of the gaseous layer in contact with the surface is zero which goes on increasing upon increasing the distance from OX towards OY (the direction perpendicular to OX) at a uniform rate . Suppose a layer ‘B’ of the gas is at a certain distance from the fixed surface OX having velocity ‘v’. Two layers ‘A’ and ‘C’ above and below are taken into consideration at a distance ‘l’ (mean free path of the gaseous molecules) so that the molecules moving vertically up and down can’t collide while moving between the two layers. Thus, the velocity of a gas in the layer ‘A’ ---------- (i) = + Likely, the velocity of the gas in the layer ‘C’ ---------- (ii) The gaseous molecules are moving in all directions due= to −thermal velocity; therefore, it may be supposed that of the gaseous molecules are moving along the three Cartesian coordinates each. -
Basics of Radiation Radiation Safety Orientation Open Source Booklet 1 (June 1, 2018)
Basics of Radiation Radiation Safety Orientation Open Source Booklet 1 (June 1, 2018) Before working with radioactive material, it is helpful to recall… Radiation is energy released from a source. • Light is a familiar example of energy traveling some distance from its source. We understand that a light bulb can remain in one place and the light can move toward us to be detected by our eyes. • The Electromagnetic Spectrum is the entire range of wavelengths or frequencies of electromagnetic radiation extending from gamma rays to the longest radio waves and includes visible light. Radioactive materials release energy with enough power to cause ionizations and are on the high end of the electromagnetic spectrum. • Although our bodies cannot sense ionizing radiation, it is helpful to think ionizing radiation behaves similarly to light. o Travels in straight lines with decreasing intensity farther away from the source o May be reflected off certain surfaces (but not all) o Absorbed when interacting with materials You will be using radioactive material that releases energy in the form of ionizing radiation. Knowing about the basics of radiation will help you understand how to work safely with radioactive material. What is “ionizing radiation”? • Ionizing radiation is energy with enough power to remove tightly bound electrons from the orbit of an atom, causing the atom to become charged or ionized. • The charged atoms can damage the internal structures of living cells. The material near the charged atom absorbs the energy causing chemical bonds to break. Are all radioactive materials the same? No, not all radioactive materials are the same. -
Radiation Safety Evidence Table
Guideline for Radiation Safety Evidence Table Citation Conclusion(s) Evidence Type Population Reference# Sample Sample size Intervention Comparision Concensus Concensus score Outcome measure Outcome 1 Chaffins JA. Radiation protection and procedures in Describes radiation protection Expert oninion VB N/A N/A N/A N/A N/A the OR. Radiol Technol . 2008;79(5): 415-428. measures and procedures for radiation protection in the OR. 2 Bindal RK, Glaze S, Ognoskie M, Tunner V, Malone The amount of radiation received by Descriptive IIIC 1 surgeon, N/A N/A 1 surgeon, 24 Radiaiton dose R, Ghosh S. Surgeon and patient radiation patients and physicians is low during 24 patients patients exposure in minimally invasive transforaminal minimally invasive transforaminal lumbar interbody fusion. J Neurosurg Spine. lumbar interbody fusion. 2008;9(6):570–573. 3 Cattani F, Vavassori A, Polo Aet al. Radiation A visitor should stay 1 meter away Descriptive, IIIC Patients N/A N/A 216 patients Radiation dose exposure after permanent prostate brachytherapy. from the patient who has radioactive retrospective Radiother Oncol. 2006;79(1):65–69. seeds implanted for a period of time equal to the half life of the radionuclide to achieve a radiation does as low as reasonably/readily achievable. 4 Brown KR, Rzucidlo E. Acute and chronic radiation Suggestions for patient education and Literature review VB N/A N/A N/A N/A N/A injury. J Vasc Surg. 2011;53(1 Suppl):15S–21S. tips to avoid injury, description of injuries from radiation, patient risk factors for injury. 5 Miller DL. Efforts to optimize radiation protection Historical review of all aspects of Literature review VA N/A N/A N/A N/A N/A in interventional fluoroscopy. -
Key Elements of X-Ray CT Physics Part 2: X-Ray Interactions
Key Elements of X-ray CT Physics Part 2: X-ray Interactions NPRE 435, Principles of Imaging with Ionizing Radiation, Fall 2006 Photoelectric Effect • Photoe- absorption is the preferred interaction for X-ray imging. 2 - •Rem.:Eb Z ; characteristic x-rays and/or Auger e preferredinhigh Zmaterial. • Probability of photoe- absorption Z3/E3 (Z = atomic no.) provide contrast according to different Z. • Due to the absorption of the incident x-ray without scatter, maximum subject contrast arises with a photoe- effect interaction No scattering contamination better contrast • Explains why contrast as higher energy x-rays are used in the imaging process - • Increased probability of photoe absorption just above the Eb of the inner shells cause discontinuities in the attenuation profiles (e.g., K-edge) NPRE 435, Principles of Imaging with Ionizing Radiation, Fall 2017 Photoelectric Effect NPRE 435, Principles of Imaging with Ionizing Radiation, Fall 2017 X-ray Cross Section and Linear Attenuation Coefficient • Cross section is a measure of the probability (‘apparent area’) of interaction: (E) measured in barns (10-24 cm2) • Interaction probability can also be expressed in terms of the thickness of the material – linear attenuation coefficient: (E) = fractional number of photons removed (attenuated) from the beam after traveling through a unit length in media by absorption or scattering -1 - • (E) [cm ]=Z[e /atom] · Navg [atoms/mole] · 1/A [moles/gm] · [gm/cm3] · (E) [cm2/e-] • Multiply by 100% to get % removed from the beam/cm • (E) as E , e.g., for soft tissue (30 keV) = 0.35 cm-1 and (100 keV) = 0.16 cm-1 NPRE 435, Principles of Imaging with Ionizing Radiation, Fall 2017 Calculation of the Linear Attenuation Coefficient To the extent that Compton scattered photons are completely removed from the beam, the attenuation coefficient can be approximated as The (effective) Z value of a material is particular important for determining . -
Shielding for Radiation Scattered Dose Distribution to the Outside Fields in Patients Treated with High Energy Radiotherapy Beams
IAEA-CN-85-70 SHIELDING FOR RADIATION SCATTERED DOSE DISTRIBUTION TO THE OUTSIDE FIELDS IN PATIENTS TREATED WITH HIGH ENERGY RADIOTHERAPY BEAMS SungSilChu XA0101718 Department of radiation Oncology, Yonsei Cancer Center, Yonsei University, Seoul, Republic of Korea Abstract Scattered dose of therapeutic high energy radiation beams are contributed significan t unwanted dose to the patient. Measurement of radiation scattered dose outside fields and critical organs, like fetus position and testicle region, from chest or pelvic irradiation by large field of high energy radiation beam was performed using an ionization chamber and film dosimetry. The scattered doses outside field were measured 5 - 10% of maximum doses in fields and exponentially decrease from field margins. The scattered photon dose received the uterus from thorax field irradiation was measured about lmGy/Gy of photon treatment dose Shielding construction to reduce this scattered dose was investigated using lead sheet and blocks About 6 cm lead block shield reduced the scatter photon dose under lOmGy for 60Gy on abdomen field and reduced almost electron contamination. 1. Introduction High energy photon beams from medical linear accelerators produce large scattered radiation by various components of the treatment head, collimator and walls or objects in the treatment room including the patient. These scattered radiation do not provide therapeutic dose and are considered a hazard from the radiation safety perspective. The scattered photon dose received the fetus from thorax field irradiation was measured about lmGy/Gy of photon treatment dose and typical therapeutic doses of photon radiation lie in the range 40 -70Gy. Thus, without additional shielding, the scattered photon dose received by the fetus might be several hundred mGy. -
Photon Cross Sections, Attenuation Coefficients, and Energy Absorption Coefficients from 10 Kev to 100 Gev*
1 of Stanaaros National Bureau Mmin. Bids- r'' Library. Ml gEP 2 5 1969 NSRDS-NBS 29 . A111D1 ^67174 tioton Cross Sections, i NBS Attenuation Coefficients, and & TECH RTC. 1 NATL INST OF STANDARDS _nergy Absorption Coefficients From 10 keV to 100 GeV U.S. DEPARTMENT OF COMMERCE NATIONAL BUREAU OF STANDARDS T X J ". j NATIONAL BUREAU OF STANDARDS 1 The National Bureau of Standards was established by an act of Congress March 3, 1901. Today, in addition to serving as the Nation’s central measurement laboratory, the Bureau is a principal focal point in the Federal Government for assuring maximum application of the physical and engineering sciences to the advancement of technology in industry and commerce. To this end the Bureau conducts research and provides central national services in four broad program areas. These are: (1) basic measurements and standards, (2) materials measurements and standards, (3) technological measurements and standards, and (4) transfer of technology. The Bureau comprises the Institute for Basic Standards, the Institute for Materials Research, the Institute for Applied Technology, the Center for Radiation Research, the Center for Computer Sciences and Technology, and the Office for Information Programs. THE INSTITUTE FOR BASIC STANDARDS provides the central basis within the United States of a complete and consistent system of physical measurement; coordinates that system with measurement systems of other nations; and furnishes essential services leading to accurate and uniform physical measurements throughout the Nation’s scientific community, industry, and com- merce. The Institute consists of an Office of Measurement Services and the following technical divisions: Applied Mathematics—Electricity—Metrology—Mechanics—Heat—Atomic and Molec- ular Physics—Radio Physics -—Radio Engineering -—Time and Frequency -—Astro- physics -—Cryogenics. -
Advanced Physics Laboratory
1 ADVANCED PHYSICS LABORATORY XRF X-Ray Fluorescence: Energy-Dispersive Technique (EDXRF) PART II Optional Experiments Author: Natalia Krasnopolskaia Last updated: N. Krasnopolskaia, January 2017 Spectrum of YBCO superconductor obtained by Oguzhan Can. SURF 2013 2 Contents Introduction ………………………………………………………………………………………3 Experiment 1. Quantitative elemental analysis of coins ……………..………………………….12 Experiment 2. Study of Si PIN detector in the x-ray fluorescence spectrometer ……………….16 Experiment 3. Secondary enhancement of x-ray fluorescence and matrix effects in alloys.……24 Experiment 4. Verification of stoichiometry formula for superconducting materials..………….29 3 INTRODUCTION In Part I of the experiment you got familiar with fundamental ideas about the origin of x-ray photons as a result of decelerating of electrons in an x-ray tube and photoelectric effect in atoms of the x-ray tube and a target. For practical purposes, the processes in the x-ray tube and in the sample of interest must be explained in detail. An X-ray photon from the x-ray tube incident on a target/sample can be either absorbed by the atoms of the target or scattered. The corresponding processes are: (a) photoelectric effect (absorption) that gives rise to characteristic spectrum emitted isotropically; (b) Compton effect (inelastic scattering; energy shifts toward the lower value); and (c) Rayleigh scattering (elastic scattering; energy of the photon stays unchanged). Each event of interaction between the incident particle and an atom or the other particle is characterized by its probability, which in spectroscopy is expressed through the cross section σ of the process. Actually, σ has a dimension of [L2] and in atomic and nuclear physics has a unit of barn: 1 barn = 10-24cm2. -
Gamma, X-Ray and Neutron Shielding Properties of Polymer Concretes
Indian Journal of Pure & Applied Physics Vol. 56, May 2018, pp. 383-391 Gamma, X-ray and neutron shielding properties of polymer concretes L Seenappaa,d, H C Manjunathaa*, K N Sridharb & Chikka Hanumantharayappac aDepartment of Physics, Government College for Women, Kolar 563 101, India bDepartment of Physics, Government First grade College, Kolar 563 101, India cDepartment of Physics, Vivekananda Degree College, Bangalore 560 055, India dResearch and Development Centre, Bharathiar University, Coimbatore 641 046, India Received 21 June 2017; accepted 3 November 2017 We have studied the X-ray and gamma radiation shielding parameters such as mass attenuation coefficient, linear attenuation coefficient, half value layer, tenth value layer, effective atomic numbers, electron density, exposure buildup factors, relative dose, dose rate and specific gamma ray constant in some polymer based concretes such as sulfur polymer concrete, barium polymer concrete, calcium polymer concrete, flourine polymer concrete, chlorine polymer concrete and germanium polymer concrete. The neutron shielding properties such as coherent neutron scattering length, incoherent neutron scattering lengths, coherent neutron scattering cross section, incoherent neutron scattering cross sections, total neutron scattering cross section and neutron absorption cross sections in the polymer concretes have been studied. The shielding properties among the studied different polymer concretes have been compared. From the detail study, it is clear that barium polymer concrete is good absorber for X-ray, gamma radiation and neutron. The attenuation parameters for neutron are large for chlorine polymer concrete. Hence, we suggest barium polymer concrete and chlorine polymer concrete are the best shielding materials for X-ray, gamma and neutrons. Keywords: X-ray, Gamma, Mass attenuation coefficient, Polymer concrete 1 Introduction Agosteo et al.11 studied the attenuation of Concrete is used for radiation shielding. -
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......................................................................................................................... -
Remote Sensing
remote sensing Article A Refined Four-Stream Radiative Transfer Model for Row-Planted Crops Xu Ma 1, Tiejun Wang 2 and Lei Lu 1,3,* 1 College of Earth and Environmental Sciences, Lanzhou University, Lanzhou 730000, China; [email protected] 2 Faculty of Geo-Information Science and Earth Observation (ITC), University of Twente, P.O. Box 217, 7500 AE Enschede, The Netherlands; [email protected] 3 Key Laboratory of Western China’s Environmental Systems (Ministry of Education), Lanzhou University, Lanzhou 730000, China * Correspondence: [email protected]; Tel.: +86-151-1721-8663 Received: 17 March 2020; Accepted: 14 April 2020; Published: 18 April 2020 Abstract: In modeling the canopy reflectance of row-planted crops, neglecting horizontal radiative transfer may lead to an inaccurate representation of vegetation energy balance and further cause uncertainty in the simulation of canopy reflectance at larger viewing zenith angles. To reduce this systematic deviation, here we refined the four-stream radiative transfer equations by considering horizontal radiation through the lateral “walls”, considered the radiative transfer between rows, then proposed a modified four-stream (MFS) radiative transfer model using single and multiple scattering. We validated the MFS model using both computer simulations and in situ measurements, and found that the MFS model can be used to simulate crop canopy reflectance at different growth stages with an accuracy comparable to the computer simulations (RMSE < 0.002 in the red band, RMSE < 0.019 in NIR band). Moreover, the MFS model can be successfully used to simulate the reflectance of continuous (RMSE = 0.012) and row crop canopies (RMSE < 0.023), and therefore addressed the large viewing zenith angle problems in the previous row model based on four-stream radiative transfer equations. -
Interim Guidelines for Hospital Response to Mass Casualties from a Radiological Incident December 2003
Interim Guidelines for Hospital Response to Mass Casualties from a Radiological Incident December 2003 Prepared by James M. Smith, Ph.D. Marie A. Spano, M.S. Division of Environmental Hazards and Health Effects, National Center for Environmental Health Summary On September 11, 2001, U.S. symbols of economic growth and military prowess were attacked and thousands of innocent lives were lost. These tragic events exposed our nation’s vulnerability to attack and heightened our awareness of potential threats. Further examination of the capabilities of foreign nations indicate that terrorist groups worldwide have access to information on the development of radiological weapons and the potential to acquire the raw materials necessary to build such weapons. The looming threat of attack has highlighted the vital role that public health agencies play in our nation’s response to terrorist incidents. Such agencies are responsible for detecting what agent was used (chemical, biological, radiological), event surveillance, distribution of necessary medical supplies, assistance with emergency medical response, and treatment guidance. In the event of a terrorist attack involving nuclear or radiological agents, it is one of CDC’s missions to insure that our nation is well prepared to respond. In an effort to fulfill this goal, CDC, in collaboration with representatives of local and state health and radiation protection departments and many medical and radiological professional organizations, has identified practical strategies that hospitals can refer