Transparency in Nuclear Warheads and Materials
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Nuclear Technology
Nuclear Technology Joseph A. Angelo, Jr. GREENWOOD PRESS NUCLEAR TECHNOLOGY Sourcebooks in Modern Technology Space Technology Joseph A. Angelo, Jr. Sourcebooks in Modern Technology Nuclear Technology Joseph A. Angelo, Jr. GREENWOOD PRESS Westport, Connecticut • London Library of Congress Cataloging-in-Publication Data Angelo, Joseph A. Nuclear technology / Joseph A. Angelo, Jr. p. cm.—(Sourcebooks in modern technology) Includes index. ISBN 1–57356–336–6 (alk. paper) 1. Nuclear engineering. I. Title. II. Series. TK9145.A55 2004 621.48—dc22 2004011238 British Library Cataloguing in Publication Data is available. Copyright © 2004 by Joseph A. Angelo, Jr. All rights reserved. No portion of this book may be reproduced, by any process or technique, without the express written consent of the publisher. Library of Congress Catalog Card Number: 2004011238 ISBN: 1–57356–336–6 First published in 2004 Greenwood Press, 88 Post Road West, Westport, CT 06881 An imprint of Greenwood Publishing Group, Inc. www.greenwood.com Printed in the United States of America The paper used in this book complies with the Permanent Paper Standard issued by the National Information Standards Organization (Z39.48–1984). 10987654321 To my wife, Joan—a wonderful companion and soul mate Contents Preface ix Chapter 1. History of Nuclear Technology and Science 1 Chapter 2. Chronology of Nuclear Technology 65 Chapter 3. Profiles of Nuclear Technology Pioneers, Visionaries, and Advocates 95 Chapter 4. How Nuclear Technology Works 155 Chapter 5. Impact 315 Chapter 6. Issues 375 Chapter 7. The Future of Nuclear Technology 443 Chapter 8. Glossary of Terms Used in Nuclear Technology 485 Chapter 9. Associations 539 Chapter 10. -
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 -
Regulations for the Control of Radiation in Mississippi Rule 1.1.18 for Applicable Fee
Title 15: Mississippi State Department of Health Part 21: Division of Radiological Health Subpart 78: Radiological Health Chapter 1 REGULATIONS FOR CONTROL OF RADIATION IN MISSISSIPPI Subchapter 1 General Provisions Rule 1.1.1 Scope. Except as otherwise specifically provided, these regulations apply to all persons who receive, possess, use, transfer, own, or acquire any source of radiation; provided, however, that nothing in these regulations shall apply to any person to the extent such person is subject to regulation by the U.S. Nuclear Regulatory Commission.1 SOURCE: Miss. Code Ann. §45-14-11 Rule 1.1.2 Definitions. As used in these regulations, these terms have the definitions set forth below. Additional definitions used only in a certain section will be found in that section. 1. "A1" means the maximum activity of special form radioactive material permitted in a Type A package. "A2" means the maximum activity of radioactive material, other than special form, LSA and SCO material, permitted in a Type A package. These values are either listed in Appendix A, Table A-1 of Subchapter 13 of these regulations or may be derived in accordance with the procedure prescribed in Appendix A of Subchapter 13 of these regulations. 2. "Absorbed dose" means the energy imparted to matter by ionizing radiation per unit mass of irradiated material at the place of interest. The units of absorbed dose are the rad and the gray (Gy). 3. "Accelerator" means any machine capable of accelerating electrons, protons, deuterons, or other charged particles in a vacuum and of discharging the resultant particulate or other radiation into a medium at energies usually in excess of 1 MeV. -
Heater Element Specifications Bulletin Number 592
Technical Data Heater Element Specifications Bulletin Number 592 Topic Page Description 2 Heater Element Selection Procedure 2 Index to Heater Element Selection Tables 5 Heater Element Selection Tables 6 Additional Resources These documents contain additional information concerning related products from Rockwell Automation. Resource Description Industrial Automation Wiring and Grounding Guidelines, publication 1770-4.1 Provides general guidelines for installing a Rockwell Automation industrial system. Product Certifications website, http://www.ab.com Provides declarations of conformity, certificates, and other certification details. You can view or download publications at http://www.rockwellautomation.com/literature/. To order paper copies of technical documentation, contact your local Allen-Bradley distributor or Rockwell Automation sales representative. For Application on Bulletin 100/500/609/1200 Line Starters Heater Element Specifications Eutectic Alloy Overload Relay Heater Elements Type J — CLASS 10 Type P — CLASS 20 (Bul. 600 ONLY) Type W — CLASS 20 Type WL — CLASS 30 Note: Heater Element Type W/WL does not currently meet the material Type W Heater Elements restrictions related to EU ROHS Description The following is for motors rated for Continuous Duty: For motors with marked service factor of not less than 1.15, or Overload Relay Class Designation motors with a marked temperature rise not over +40 °C United States Industry Standards (NEMA ICS 2 Part 4) designate an (+104 °F), apply application rules 1 through 3. Apply application overload relay by a class number indicating the maximum time in rules 2 and 3 when the temperature difference does not exceed seconds at which it will trip when carrying a current equal to 600 +10 °C (+18 °F). -
602 Public Law 88-4S8~Aug. 22, 1964 [78 Stat
602 PUBLIC LAW 88-4S8~AUG. 22, 1964 [78 STAT. such agency, if the assistance or progam will promote the welfare of the Trust Territory, notwithstanding any provision of law under which the Trust Territory may otherwise be ineligible for the assist ance or program: Provided^ That the Secretary of the Interior shall not request assistance pursuant to this subsection that involves, in the aggregate, an estimated nonreimbursable cost in any one fiscal year in excess of $150,000: Provided further. That the cost of any program extended to the Trust Territory under this subsection shall be reim bursable out of appropriations authorized and made for the govern 48 use 1681 note. ment of the Trust Territory pursuant to section 2 of this Act, as amended. The provisions of this subsection shall not apply to finan cial assistance under a grant-in-aid program." SEC. 2. Subsection 303(1) of the Communications Act of 1934 (48. 76 Stat. 64. Stat. 1082), as amended (47 U.S.C. 303(1)), is hereby amended by inserting the words: ", or citizens of the Trust Territory of the Pacific Islands presenting valid identity certificates issued by the High Com missioner of such Territory," immediately following the words "citi zens or nationals of the United States". Revolving fund, abolishment. SEC. 3. The revolving fund authorized by the Department of the Interior and Related Agencies Appropriation Act, 1956 (69 Stat. 141, 149), to be available during fiscal year 1956 for loans to locally owned private training companies in the Trust Territory of the Pacific Islands, which revolving fund has been continued by subsequent annual appropriation Acts, is hereby abolished, and the total assets of the revolving fund are contributed as a grant to the government of the Trust Territory for use as a development fund within the Trust Territory of the Pacific Islands. -
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. -
State-Of-The-Art Mobile Radiation Detection Systems for Different Scenarios
sensors Review State-of-the-Art Mobile Radiation Detection Systems for Different Scenarios Luís Marques 1,* , Alberto Vale 2 and Pedro Vaz 3 1 Centro de Investigação da Academia da Força Aérea, Academia da Força Aérea, Instituto Universitário Militar, Granja do Marquês, 2715-021 Pêro Pinheiro, Portugal 2 Instituto de Plasmas e Fusão Nuclear, Instituto Superior Técnico, Universidade de Lisboa, Av. Rovisco Pais 1, 1049-001 Lisboa, Portugal; [email protected] 3 Centro de Ciências e Tecnologias Nucleares, Instituto Superior Técnico, Universidade de Lisboa, Estrada Nacional 10 (km 139.7), 2695-066 Bobadela, Portugal; [email protected] * Correspondence: [email protected] Abstract: In the last decade, the development of more compact and lightweight radiation detection systems led to their application in handheld and small unmanned systems, particularly air-based platforms. Examples of improvements are: the use of silicon photomultiplier-based scintillators, new scintillating crystals, compact dual-mode detectors (gamma/neutron), data fusion, mobile sensor net- works, cooperative detection and search. Gamma cameras and dual-particle cameras are increasingly being used for source location. This study reviews and discusses the research advancements in the field of gamma-ray and neutron measurements using mobile radiation detection systems since the Fukushima nuclear accident. Four scenarios are considered: radiological and nuclear accidents and emergencies; illicit traffic of special nuclear materials and radioactive -
SENATE BILL No. 125
{As Amended by Senate Committee of the Whole} Session of 2015 SENATE BILL No. 125 By Committee on Natural Resources 2-2 1 AN ACT concerning radioactive materials; relating to by-product material; 2 low-level radioactive waste; naturally occurring radioactive material; 3 amending K.S.A. 48-1603 and 48-1620 and repealing the existing 4 sections. 5 6 Be it enacted by the Legislature of the State of Kansas: 7 Section 1. K.S.A. 48-1603 is hereby amended to read as follows: 48- 8 1603. As used in this act: 9 (a) "By-product material" means: (1) Any radioactive material, except 10 special nuclear material, yielded in or made radioactive by exposure to the 11 radiation incident to the process of producing or utilizing special nuclear 12 material; and 13 (2) the tailings or wastes produced by the extraction or concentration of 14 uranium or thorium from any ore processed primarily for its source 15 material content; 16 (3) any discrete source of radium-226 that is produced, extracted or 17 converted after extraction for use for a commercial, medical or research 18 activity; and 19 (4) any material that: 20 (A) Has been made radioactive by use of a particle accelerator; and 21 (B) is produced, extracted or converted after extraction for use for a 22 commercial, medical or research activity; or 23 (5) any discrete source of naturally occurring radioactive material, 24 other than source material, that: 25 (A) The secretary declares by order would pose a threat to the public 26 health and safety or the common defense and security similar to the threat 27 posed by a discrete source of radium-226 after the United States nuclear 28 regulatory commission, or any successor thereto, determines the same; 29 and 30 (B) is extracted or converted after extraction for use in a commercial, 31 medical or research activity. -
611130 Outgoing Amendment No. 52 to Curium US LLC to License No
NRCFORM374 PAGE 1 OF 5 PAGES U.S. NUCLEAR REGULATORY COMMISSION Amendment No. 52 MATERIALS LICENSE Pursuant to the Atomic Energy Act of 1954, as amended, the Energy Reorganization Act of 1974 (Public Law 93-438), and Title 10, Code of Federal Regulations, Chapter I, Parts 30, 31, 32, 33, 34, 35, 36, 37, 39, 40, 70 and 71, and in reliance on statements and representations heretofore made by the licensee, a license is hereby issued authorizing the licensee to receive, acquire, possess, and transfer byproduct, source, and special nuclear material designated below; to use such material for the purpose(s) and at the place(s) designated below; to deliver or transfer such material to persons authorized to receive it in accordance with the regulations of the applicable Part(s). This license shall be deemed to contain the conditions specified in Section 183 of the Atomic Energy Act of 1954, as amended, and is subject to all applicable rules, regulations, and orders of the Nuclear Regulatory Commission now or hereafter in effect and to any conditions specified below. Licensee In accordance with letter dated 4. Expiration Date: July 31, 2022 Janua~22...2.0J», 1. Curium US LLC ~~t\ Kt:G t----------..iii-,..iii-,--1 5. Docket No.: 030-10801 2. 2703 Wagner Place 3. license No.: 24-04206-05f\A[() Reference No.: Maryland Heights, MO 63043 is amended in Its entirety to re~ as follows: i!" 1 ~i\il'W, 6. Byproduct, source, 7. Chemical ahttor physical form 8. Maximum amount that lice~e·~ 9. Authorized use and/or special nuclear may possess at any one tfmel material this license A. -
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. -
April 4, 2003, Board Letter Establishing a 60-Day Reporting
John T. Conway, Chairman A.J. Eggenbe,ger, Vice Chairman DEFENSE NUCLFAR FACILITIES John E. Mansfield SAFE'IY BOARD 625 Indiana Avenue, NW, Suite 700, Washington, D.C. 20004-2901 (202) 694-7000 April 4, 2003 The Honorable Linton Brooks Acting Administrator of the National Nuclear Security Administration U.S. Department ofEnergy 1000 Independence A venue, SW Washington, DC 20585-0701 Dear Ambassador Brooks: During the past 16 months, the Defense Nuclear Facilities Safety Board (Board) has held a number of reviews at the Pantex Plant to evaluate conduct ofoperations and the site's training programs. The Board is pleased to see that procedural adherence and conduct ofoperations for operational personnel are improving and that a program to improve operating procedures is ongoing. However, a review by the Board's staff has revealed problems at Pantex with the processes used to develop training, to evaluate personnel knowledge, to assess training program elements, and to conduct continuing training. These training deficiencies, detailed in the enclosed report, may affect the ability to improve and maintain satisfactory conduct of operations at the Pantex Plant. Therefore, pursuant to 42 U.S.C. § 2286b(d), the Board requests a report within the next 60 days regarding the measures that are being taken to address these training deficiencies. Sincerely, c: The Honorable Everet H. Beckner Mr. Daniel E. Glenn Mr. Mark B. Whitaker, Jr. Enclosure DEFENSE NUCLEAR FACILITIES SAFETY BOARD Staff Issue Report March 24, 2003 MEMORANDUM FOR: J. K. Fortenberry, Technical Director COPIES: Board Members FROM: J. Deplitch SUBJECT: Conduct ofOperations and Training Programs at the Pantex Plant This report documents a review by the staff ofthe Defense Nuclear Facilities Safety Board (Board) ofconduct ofoperations and the training programs at the Pantex Plant.