Introduction to International Safeguards
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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 -
Pakistan's Nuclear Weapons
Pakistan’s Nuclear Weapons Paul K. Kerr Analyst in Nonproliferation Mary Beth Nikitin Specialist in Nonproliferation August 1, 2016 Congressional Research Service 7-5700 www.crs.gov RL34248 Pakistan’s Nuclear Weapons Summary Pakistan’s nuclear arsenal probably consists of approximately 110-130 nuclear warheads, although it could have more. Islamabad is producing fissile material, adding to related production facilities, and deploying additional nuclear weapons and new types of delivery vehicles. Pakistan’s nuclear arsenal is widely regarded as designed to dissuade India from taking military action against Pakistan, but Islamabad’s expansion of its nuclear arsenal, development of new types of nuclear weapons, and adoption of a doctrine called “full spectrum deterrence” have led some observers to express concern about an increased risk of nuclear conflict between Pakistan and India, which also continues to expand its nuclear arsenal. Pakistan has in recent years taken a number of steps to increase international confidence in the security of its nuclear arsenal. Moreover, Pakistani and U.S. officials argue that, since the 2004 revelations about a procurement network run by former Pakistani nuclear official A.Q. Khan, Islamabad has taken a number of steps to improve its nuclear security and to prevent further proliferation of nuclear-related technologies and materials. A number of important initiatives, such as strengthened export control laws, improved personnel security, and international nuclear security cooperation programs, have improved Pakistan’s nuclear security. However, instability in Pakistan has called the extent and durability of these reforms into question. Some observers fear radical takeover of the Pakistani government or diversion of material or technology by personnel within Pakistan’s nuclear complex. -
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. -
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. -
NRC Submittal Rule Text for Oklahoma Title 252, Chapter
TITLE 252. DEPARTMENT OF ENVIRONMENTAL QUALITY CHAPTER 410. RADIATION MANAGEMENT SUBCHAPTER 1. GENERAL PROVISIONS 252:410-1-7. Incorporation of federal regulations by reference (a) 10 CFR. References in this Chapter to Title 10 of the Code of Federal Regulations (10 CFR) mean the January 1, 2016January 1, 2019 publication of 10 CFR. (b) 40 CFR. References in this Chapter to Title 40 of the Code of Federal Regulations (40 CFR) mean the July 1, 1998 publication of 40 CFR and 64 Fed. Reg. 5574 (February 3, 1999). (c) Citations incorporated. When a provision of the Code of Federal Regulations is incorporated by reference, all citations contained therein are also incorporated by reference. SUBCHAPTER 10. RADIOACTIVE MATERIALS PROGRAM PART 1. GENERAL PROVISIONS 252:410-10-1. Radioactive Materials Program (a) Scope. (1) The rules in this Subchapter establish license requirements for the following categories of radioactive materials: byproduct material, source material and special nuclear material. (2) License requirements incorporated by reference from 10 CFR are applicable requirements for all categories of radioactive materials within the scope of this Subchapter. (b) Exclusions. Responsibility for the following regulatory requirements remains with the NRC: (1) In 10 CFR 20. Exemptions to labeling requirements, § 20.1905(g); Reports of exposures, radiation levels, and concentrations of radioactive material exceeding the constraints or limits at nuclear power plants, § 20.2203(c); Reports of individual monitoring, § 20.2206(a)(1), (a)(3), (a)(4) and (a)(5); (2) In 10 CFR 30. Activities requiring license, § 30.3(b); Definitions, 30.4 "Commencement of construction" paragraph (2), "Construction" paragraph (9)(ii), and "Quantities of concern"; Application for specific licenses, § 30.32(k); Terms and conditions of licenses, § 30.34 (d), (e)(1), (e)(3) and (1); Transfer of byproduct material, § 30.41 (b)(6); Tritium reports, § 30.55; (3) In 10 CFR 32. -
DOE-OC Green Book
SUBJECT AREA INDICATORS AND KEY WORD LIST FOR RESTRICTED DATA AND FORMERLY RESTRICTED DATA U.S. DEPARTMENT OF ENERGY AUGUST 2018 TABLE OF CONTENTS PURPOSE ....................................................................................................................................................... 1 BACKGROUND ............................................................................................................................................... 2 Where It All Began .................................................................................................................................... 2 DIFFERENCE BETWEEN RD/FRD and NATIONAL SECURITY INFORMATION (NSI) ......................................... 3 ACCESS TO RD AND FRD ................................................................................................................................ 4 Non-DoD Organizations: ........................................................................................................................... 4 DoD Organizations: ................................................................................................................................... 4 RECOGNIZING RD and FRD ............................................................................................................................ 5 Current Documents ................................................................................................................................... 5 Historical Documents ............................................................................................................................... -
Highly Enriched Uranium: Striking a Balance
OFFICIAL USE ONLY - DRAFT GLOSSARY OF TERMS APPENDIX F GLOSSARY OF TERMS Accountability: That part of the safeguards and security program that encompasses the measurement and inventory verification systems, records, and reports to account for nuclear materials. Assay: Measurement that establishes the total quantity of the isotope of an element and the total quantity of that element. Atom: The basic component of all matter. Atoms are the smallest part of an element that have all of the chemical properties of that element. Atoms consist of a nucleus of protons and neutrons surrounded by electrons. Atomic energy: All forms of energy released in the course of nuclear fission or nuclear transformation. Atomic weapon: Any device utilizing atomic energy, exclusive of the means for transportation or propelling the device (where such means is a separable and divisible part of the device), the principal purpose of which is for use as, or for development of, a weapon, a weapon prototype, or a weapon test device. Blending: The intentional mixing of two different assays of the same material in order to achieve a desired third assay. Book inventory: The quantity of nuclear material present at a given time as reflected by accounting records. Burnup: A measure of consumption of fissionable material in reactor fuel. Burnup can be expressed as (a) the percentage of fissionable atoms that have undergone fission or capture, or (b) the amount of energy produced per unit weight of fuel in the reactor. Chain reaction: A self-sustaining series of nuclear fission reactions. Neutrons produced by fission cause more fission. Chain reactions are essential to the functioning of nuclear reactors and weapons. -
How Nuclear Energy Is Collected and Distributed
Professor Max Powers’ Power Efficiency Project (PEP) is brought to you by the Kansas Corporation Commission and Kansas State University Engineering Extension. Funding provided by a grant from the U.S. Department of Energy. Professor Max Powers How Nuclear Energy is Collected and Distributed What is Nuclear Fission? Figure 1: Example of Nuclear Fission. An atom is the smallest unit of matter that maintains the Source: https://www.energy.gov/sites/prod/files/The%20History%20of%20 Nuclear%20Energy_0.pdf properties of a chemical element. It consists of a nucleus (which contains densely packed protons and neutrons) surrounded by electrons. When “bombarded” with a neutron, an atom can be split apart.1 A nuclear material is any element that splits apart easily. Hydrogen is the lightest element containing only one proton, and uranium is the heaviest naturally-occurring element with 92 protons. Since uranium is relatively larger, the bonds holding it together are much weaker and can be split more easily. Thus, isotopes of uranium are used in most nuclear power plants. A nuclear reactor combines neutrons with the nuclear material to cause a fission chain reaction. Fission is the process of splitting isotopes of an element to release energy as heat. A series of fission is called a chain reaction as seen in Figure 1. When enough isotopes are added to the process (termed the critical mass), the reaction becomes Using Nuclear Energy to Generate a self-sustaining chain reaction which releases enough energy Electricity to boil water and generate steam to turn turbines. There are two designs for nuclear reactors: pressurized water One advantage of using nuclear material for electricity reactor and boiling water reactor. -
IAEA Annual Report 2001
ANNUAL REPORT 2001 INTERNATIONAL ATOMIC ENERGY AGENCY Picture credits: PhotoDisc; Third photo on left: D. Kinley, IAEA INTERNATIONAL ATOMIC ENERGY AGENCY ANNUAL REPORT 2001 Article VI.J of the Agency’s Statute requires the Board of Governors to submit “an annual report to the General Conference concerning the affairs of the Agency and any projects approved by the Agency”. This report covers the period 1 January to 31 December 2001. GC(46)/2 MEMBER STATES OF THE INTERNATIONAL ATOMIC ENERGY AGENCY (as of 31 December 2001) AFGHANISTAN GREECE PARAGUAY ALBANIA GUATEMALA PERU ALGERIA HAITI PHILIPPINES ANGOLA HOLY SEE POLAND ARGENTINA HUNGARY PORTUGAL ARMENIA ICELAND QATAR AUSTRALIA INDIA REPUBLIC OF MOLDOVA AUSTRIA INDONESIA ROMANIA AZERBAIJAN IRAN, ISLAMIC REPUBLIC OF RUSSIAN FEDERATION BANGLADESH IRAQ SAUDI ARABIA BELARUS IRELAND SENEGAL BELGIUM ISRAEL SIERRA LEONE BENIN ITALY SINGAPORE BOLIVIA JAMAICA SLOVAKIA BOSNIA AND HERZEGOVINA JAPAN SLOVENIA BRAZIL JORDAN SOUTH AFRICA BULGARIA KAZAKHSTAN SPAIN BURKINA FASO KENYA SRI LANKA CAMBODIA KOREA, REPUBLIC OF SUDAN CAMEROON KUWAIT SWEDEN CANADA LATVIA SWITZERLAND CENTRAL AFRICAN LEBANON SYRIAN ARAB REPUBLIC REPUBLIC LIBERIA TAJIKISTAN CHILE LIBYAN ARAB JAMAHIRIYA THAILAND CHINA LIECHTENSTEIN COLOMBIA LITHUANIA THE FORMER YUGOSLAV COSTA RICA LUXEMBOURG REPUBLIC OF MACEDONIA CÔTE D’IVOIRE MADAGASCAR TUNISIA CROATIA MALAYSIA TURKEY CUBA MALI UGANDA CYPRUS MALTA UKRAINE CZECH REPUBLIC MARSHALL ISLANDS UNITED ARAB EMIRATES DEMOCRATIC REPUBLIC MAURITIUS UNITED KINGDOM OF OF THE CONGO MEXICO GREAT BRITAIN -
Nuclear Fuel Cycles Technology Assessment
Clean Power Quadrennial Technology Review 2015 Chapter 4: Advancing Clean Electric Power Technologies Technology Assessments Advanced Plant Technologies Biopower Carbon Dioxide Capture and Storage Clean Power Value-Added Options Carbon Dioxide Capture for Natural Gas and Industrial Applications Carbon Dioxide Capture Technologies Carbon Dioxide Storage Technologies Crosscutting Technologies in Carbon Dioxide Capture and Storage Fast-spectrum Reactors Geothermal Power High Temperature Reactors Hybrid Nuclear-Renewable Energy Systems Hydropower Light Water Reactors Marine and Hydrokinetic Power Nuclear Fuel Cycles Solar Power Stationary Fuel Cells Supercritical Carbon Dioxide Brayton Cycle U.S. DEPARTMENT OF Wind Power ENERGY Clean Power Quadrennial Technology Review 2015 Nuclear Fuel Cycles Chapter 4: Technology Assessments Introduction and Background The Nuclear Fuel Cycle (NFC) is defined as the total set of operations required to produce fission energy and manage the associated nuclear materials. It can have different attributes, including the extension of natural resources, or the minimization of waste disposal requirements. The NFC, as depicted in Figure 4.O.1, is comprised of a set of operations that include the extraction of uranium (U) resources from the earth (and possibly from seawater), uranium enrichment and fuel fabrication, use of the fuel in reactors, interim storage of used nuclear fuel, the optional recycle of the used fuel, and the final disposition of used fuel and waste forms from the recycling processes. Thorium (Th) fuel cycles have been proposed also, but have not been commercially implemented). Figure 4.O.1 Schematic of the uranium based Nuclear Fuel Cycle 1 Quadrennial Technology Review 2015 Clean Power TA 4.O: Nuclear Fuel Cycles The nuclear fuel cycle is often grouped into three classical components (front-end, reactor, and back-end): Front End: The focus of the front end of the nuclear fuel cycle is to deliver fabricated fuel to the reactor.