Identification of Radioactive Sources and Devices
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Section 1: Introduction (PDF)
SECTION 1: Introduction SECTION 1: INTRODUCTION Section 1 Contents The Purpose and Scope of This Guidance ....................................................................1-1 Relationship to CZARA Guidance ....................................................................................1-2 National Water Quality Inventory .....................................................................................1-3 What is Nonpoint Source Pollution? ...............................................................................1-4 Watershed Approach to Nonpoint Source Pollution Control .......................................1-5 Programs to Control Nonpoint Source Pollution...........................................................1-7 National Nonpoint Source Pollution Control Program .............................................1-7 Storm Water Permit Program .......................................................................................1-8 Coastal Nonpoint Pollution Control Program ............................................................1-8 Clean Vessel Act Pumpout Grant Program ................................................................1-9 International Convention for the Prevention of Pollution from Ships (MARPOL)...................................................................................................1-9 Oil Pollution Act (OPA) and Regulation ....................................................................1-10 Sources of Further Information .....................................................................................1-10 -
NUREG-1350, Vol. 31, Information
NRC Figure 31. Moisture Density Guage Bioshield Gauge Surface Detectors Depth Radiation Source GLOSSARY 159 GLOSSARY Glossary (Abbreviations, Definitions, and Illustrations) Advanced reactors Reactors that differ from today’s reactors primarily by their use of inert gases, molten salt mixtures, or liquid metals to cool the reactor core. Advanced reactors can also consider fuel materials and designs that differ radically from today’s enriched-uranium dioxide pellets within zirconium cladding. Agreement State A U.S. State that has signed an agreement with the U.S. Nuclear Regulatory Commission (NRC) authorizing the State to regulate certain uses of radioactive materials within the State. Atomic energy The energy that is released through a nuclear reaction or radioactive decay process. One kind of nuclear reaction is fission, which occurs in a nuclear reactor and releases energy, usually in the form of heat and radiation. In a nuclear power plant, this heat is used to boil water to produce steam that can be used to drive large turbines. The turbines drive generators to produce electrical power. NUCLEUS FRAGMENT Nuclear Reaction NUCLEUS NEW NEUTRON NEUTRON Background radiation The natural radiation that is always present in the environment. It includes cosmic radiation that comes from the sun and stars, terrestrial radiation that comes from the Earth, and internal radiation that exists in all living things and enters organisms by ingestion or inhalation. The typical average individual exposure in the United States from natural background sources is about 310 millirem (3.1 millisievert) per year. 160 8 GLOSSARY 8 Boiling-water reactor (BWR) A nuclear reactor in which water is boiled using heat released from fission. -
Rulemaking for Enhanced Security of Special Nuclear Material
Rulemaking for Enhanced Security of Special Nuclear Material RIN number: 3150-AJ41 NRC Docket ID: NRC-2014-0118 Regulatory Basis Document January 2015 Table of Contents 1. Introduction and Background .............................................................................................. 1 2. Existing Regulatory Framework .......................................................................................... 3 2.1 Regulatory History ............................................................................................................. 3 2.2 Existing Regulatory Requirements .................................................................................... 8 3. Regulatory Problem .......................................................................................................... 13 3.1 Generic Applicability of Security Orders .......................................................................... 13 3.2 Risk Insights .................................................................................................................... 16 3.3 Consistency and Clarity .................................................................................................. 27 3.4 Use of a Risk-Informed and Performance-Based Structure. ........................................... 29 4. Basis for Requested Changes ........................................................................................... 30 4.1 Material Categorization and Attractiveness ..................................................................... 30 4.2 -
PART I GENERAL PROVISIONS R12 64E-5.101 Definitions
64E-5 Florida Administrative Code Index PART I GENERAL PROVISIONS R12 64E-5.101 Definitions ................................................................................................. I-1 64E-5.102 Exemptions ............................................................................................. I-23 64E-5.103 Records ................................................................................................... I-24 64E-5.104 Tests ... ................................................................................................... I-24 64E-5.105 Prohibited Use ........................................................................................ I-24 64E-5.106 Units of Exposure and Dose ................................................................... I-25 64E-5 Florida Administrative Code Index 64E-5 Florida Administrative Code Index PART II LICENSING OF RADIOACTIVE MATERIALS R2 64E-5.201 ...... Licensing of Radioactive Material .............................................................. II-1 64E-5.202 ...... Source Material - Exemptions .................................................................... II-2 R12 64E-5.203 ...... Radioactive Material Other than Source Material - Exemptions ................. II-4 SUBPART A LICENSE TYPES AND FEES R12 64E-5.204 ..... Types of Licenses ..................................................................................... II-13 SUBPART B GENERAL LICENSES 64E-5.205 ..... General Licenses - Source Material ......................................................... -
Sources and Emissions of Air Pollutants
© Jones & Bartlett Learning, LLC. NOT FOR SALE OR DISTRIBUTION Chapter 2 Sources and Emissions of Air Pollutants LEArning ObjECtivES By the end of this chapter the reader will be able to: • distinguish the “troposphere” from the “stratosphere” • define “polluted air” in relation to various scientific disciplines • describe “anthropogenic” sources of air pollutants and distinguish them from “natural” sources • list 10 sources of indoor air contaminants • identify three meteorological factors that affect the dispersal of air pollutants ChAPtEr OutLinE I. Introduction II. Measurement Basics III. Unpolluted vs. Polluted Air IV. Air Pollutant Sources and Their Emissions V. Pollutant Transport VI. Summary of Major Points VII. Quiz and Problems VIII. Discussion Topics References and Recommended Reading 21 2 N D R E V I S E 9955 © Jones & Bartlett Learning, LLC. NOT FOR SALE OR DISTRIBUTION 22 Chapter 2 SourCeS and EmiSSionS of Air PollutantS i. IntrOduCtiOn level. Mt. Everest is thus a minute bump on the globe that adds only 0.06 percent to the Earth’s diameter. Structure of the Earth’s Atmosphere The Earth’s atmosphere consists of several defined layers (Figure 2–1). The troposphere, in which all life The Earth, along with Mercury, Venus, and Mars, is exists, and from which we breathe, reaches an altitude of a terrestrial (as opposed to gaseous) planet with a per- about 7–8 km at the poles to just over 13 km at the equa- manent atmosphere. The Earth is an oblate (slightly tor: the mean thickness being 9.1 km (5.7 miles). Thus, flattened) sphere with a mean diameter of 12,700 km the troposphere represents a very thin cover over the (about 8,000 statute miles). -
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. -
Consideration of Low Enriched Uranium Space Reactors
AlM Propul~oo aoo Eo«gy Forum 10.25 1416 .20 18~3 Jllly9-11, 2018,0ncinoaoi,Obio 2018 Joi.ot PropuiS;ion Confereoce Chock fof updates Consideration of Low Enriched Uranium Space Reactors David Lee Black, Ph.D. 1 Retired, Formerly Westinghouse Electric Corporation, Washington, DC, 20006. USA The Federal Government (NASA, DOE) has recently shown interest in low enrichment uranium (LEU) reactors for space power and propulsion through its studies at national laboratories and a contract with private industry. Several non-governmental organizations have strongly encouraged this approach for nuclear non-proliferation and safety reasons. All previous efforts have been with highly enriched uranium (HEU) reactors. This study evaluates and compares the effects of changing from HEU reactors with greater than 90% U-235 to LEU with less than 20% U-235. A simple analytic approach was used, the validity of which has been established by comparison with existing test data for graphite fuel only. This study did not include cermet fuel. Four configurations were analyzed: NERVA NRX, LANL's SNRE, LEU, and generic critical HEU and LEU reactors without a reflector. The nuclear criticality multiplication factor, size, weight and system thermodynamic performance were compared, showing the strong dependence on moderator-to-fuel ratio in the reactor. The conclusions are that LEU reactors can be designed to meet mission requirements of lifetime and operability. It ,.;u be larger and heavier by about 4000 lbs than a highly enriched uranium reactor to meet the same requirements. Mission planners should determine the penalty of the added weight on payload. The amount ofU-235 in an HEU core is not significantly greater in an LEU design with equal nuclear requirements. -
Re-Examining the Role of Nuclear Fusion in a Renewables-Based Energy Mix
Re-examining the Role of Nuclear Fusion in a Renewables-Based Energy Mix T. E. G. Nicholasa,∗, T. P. Davisb, F. Federicia, J. E. Lelandc, B. S. Patela, C. Vincentd, S. H. Warda a York Plasma Institute, Department of Physics, University of York, Heslington, York YO10 5DD, UK b Department of Materials, University of Oxford, Parks Road, Oxford, OX1 3PH c Department of Electrical Engineering and Electronics, University of Liverpool, Liverpool, L69 3GJ, UK d Centre for Advanced Instrumentation, Department of Physics, Durham University, Durham DH1 3LS, UK Abstract Fusion energy is often regarded as a long-term solution to the world's energy needs. However, even after solving the critical research challenges, engineer- ing and materials science will still impose significant constraints on the char- acteristics of a fusion power plant. Meanwhile, the global energy grid must transition to low-carbon sources by 2050 to prevent the worst effects of climate change. We review three factors affecting fusion's future trajectory: (1) the sig- nificant drop in the price of renewable energy, (2) the intermittency of renewable sources and implications for future energy grids, and (3) the recent proposition of intermediate-level nuclear waste as a product of fusion. Within the scenario assumed by our premises, we find that while there remains a clear motivation to develop fusion power plants, this motivation is likely weakened by the time they become available. We also conclude that most current fusion reactor designs do not take these factors into account and, to increase market penetration, fu- sion research should consider relaxed nuclear waste design criteria, raw material availability constraints and load-following designs with pulsed operation. -
Nuclear Regulatory Commission § 70.5
Nuclear Regulatory Commission § 70.5 section 51 of the act, determines to be intermediates, which are unsuitable for special nuclear material, but does not use in their present form, but all or include source material; or (2) any ma- part of which will be used after further terial artificially enriched by any of processing. the foregoing but does not include Strategic special nuclear material source material; means uranium-235 (contained in ura- Special nuclear material of low strategic nium enriched to 20 percent or more in significance means: the U235 isotope), uranium-233, or pluto- (1) Less than an amount of special nium. nuclear material of moderate strategic Transient shipment means a shipment significance as defined in paragraph (1) of nuclear material, originating and of the definition of strategic nuclear terminating in foreign countries, on a material of moderate strategic signifi- vessel or aircraft which stops at a cance in this section, but more than 15 United States port. grams of uranium-235 (contained in Unacceptable performance deficiencies uranium enriched to 20 percent or more mean deficiencies in the items relied in U-235 isotope) or 15 grams of ura- on for safety or the management meas- nium-233 or 15 grams of plutonium or ures that need to be corrected to en- the combination of 15 grams when com- sure an adequate level of protection as puted by the equation, grams = (grams defined in 10 CFR 70.61(b), (c), or (d). contained U-235) + (grams plutonium) + United States, when used in a geo- (grams U-233); or graphical sense, includes Puerto Rico (2) Less than 10,000 grams but more and all territories and possessions of than 1,000 grams of uranium-235 (con- the United States. -
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. -
RADIOACTIVE MATERIALS SECTION Revisions 3 and 4 Filing Instructions
Jeb Bush John O. Agwunobi, M.D., M.B.A Governor Acting Secretary August 2001 Bureau of Radiation Control RADIOACTIVE MATERIALS SECTION Information Notice 2001-04 Revisions 3 and 4 Filing Instructions: Changes to Chapter 64E-5, Florida Administrative Code (F.A.C.) Changes were made to “Control of Radiation Hazard Regu lations,” Chapter 64E-5, F.A.C., that became effective August 8 and September 11, 2001. These changes are indicated as Revision 3 or (R3) and Revision 4 (R4) in the margin. Enclosed are copies of the pages to be inserted. This update is printed on blue paper. These instructions apply to the complete version (brown cover) of Chapter 64E -5, F.A.C. Be sure that Revision 1 and Revision 2 changes have been made before making these changes. This can be verified by checking page ii of the index. PART PAGES TO BE REMOVED PAGES TO BE INSERTED Page Number Page Number Index i through xii i through xii I Part I Index Part I Index General Provisions I-1 through I-22 I-1 through I-22 II Part II Index Part II Index Licensing of Radioactive II-45 through II-46 II-45 through II-46 Materials II-53 through II-54 II-53 through II-54 IV Part IV Index Part IV Index Radiation Safety Requirements IV-1 through IV-16 IV-1 through IV-24 for Industrial Radiographic Operations VI Part VI Index Part VI Index Use of Radionuclides in the VI-1 through VI-2 VI-1 through VI-2 Healing Arts VI-5 through VI-6 VI-5 through VI-6 VI-23 through VI-26 VI-23 through VI-26 Attachment Attachment page not Attachment not numbered Certificate – Disposition of numbered (mailing -
Nrc Regulatory Issue Summary 2005-23 Clarification of the Physical Presence Requirement During Gamma Stereotactic Radiosurgery Treatments
UNITED STATES NUCLEAR REGULATORY COMMISSION OFFICE OF NUCLEAR MATERIAL SAFETY AND SAFEGUARDS WASHINGTON, D.C. 20555 October 7, 2005 NRC REGULATORY ISSUE SUMMARY 2005-23 CLARIFICATION OF THE PHYSICAL PRESENCE REQUIREMENT DURING GAMMA STEREOTACTIC RADIOSURGERY TREATMENTS ADDRESSEES All gamma stereotactic radiosurgery (GSR) licensees. INTENT The U.S. Nuclear Regulatory Commission (NRC) is issuing this regulatory issue summary (RIS) to clarify the definition of the term “physically present,” as used in 10 CFR 35.615(f)(3). No specific action or written response is required. BACKGROUND In March 2005, during a licensing visit to a GSR facility, the NRC staff observed that the authorized medical physicist (AMP) did not remain physically present throughout one of the GSR treatments, as required by 10 CFR 35.615(f)(3). Instead, during the treatment, the AMP walked to the other end of the GSR suite and entered a treatment planning room located more than 30.5 meters (100 feet) away from the GSR treatment console. While discussing this incident with the licensee, the NRC staff recognized that the licensee was misinterpreting the physical presence requirement for GSR treatments. Based on the licensee’s interpretation of the regulations, the licensee considered any location within the GSR suite, including the treatment planning room, to be within hearing distance of normal voice from the GSR treatment console. The licensee believed that, within the contiguous boundary of its GSR suite, the human voice has sufficient volume, without electronic amplification, to alert the AMP of an emergency at essentially any location within its suite and the AMP could respond in a timely manner.