Radioactive Waste Streams: Waste Classification for Disposal
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The Nuclear Waste Primer September 2016 What Is Nuclear Waste?
The Nuclear Waste Primer September 2016 What is Nuclear Waste? Nuclear waste is the catch-all term for anything contaminated with radioactive material. Nuclear waste can be broadly divided into three categories: • Low-level waste (LLW), comprised of protective clothing, medical waste, and other lightly-contaminated items • Transuranic waste (TRU), comprised of long-lived isotopes heavier than uranium • High-level waste (HLW), comprised of spent nuclear fuel and other highly-radioactive materials Low-level waste is relatively short-lived and easy to handle. Currently, four locations for LLW disposal exist in the United States. Two of them, Energy Solutions in Clive, Utah and Waste Control Specialists in Andrews, Texas, accept waste from any U.S. state. Transuranic waste is often a byproduct of nuclear weapons production and contains long-lived radioactive elements heavier than uranium, like plutonium and americium. Currently, the U.S. stores TRU waste at the Waste Isolation Pilot Plant (WIPP) near Carlsbad, New Mexico. High-level waste includes spent nuclear fuel and the most radioactive materials produced by nuclear weapons production. Yucca Mountain is the currently designated high-level waste repository for the United States. 1 | What is Spent Nuclear Fuel? Spent nuclear fuel (SNF), alternatively referred to as used nuclear fuel, is the primary byproduct of nuclear reactors. In commercial power reactors in the U.S., fuel begins as uranium oxide clad in a thin layer of zirconium-aluminum cladding. After several years inside of the reactor, around fi ve percent of the uranium has been converted in some way, ranging from short-lived and highly radioactive fi ssion products to long-lived actinides like plutonium, americium, and neptunium. -
FT/P3-20 Physics and Engineering Basis of Multi-Functional Compact Tokamak Reactor Concept R.M.O
FT/P3-20 Physics and Engineering Basis of Multi-functional Compact Tokamak Reactor Concept R.M.O. Galvão1, G.O. Ludwig2, E. Del Bosco2, M.C.R. Andrade2, Jiangang Li3, Yuanxi Wan3 Yican Wu3, B. McNamara4, P. Edmonds, M. Gryaznevich5, R. Khairutdinov6, V. Lukash6, A. Danilov7, A. Dnestrovskij7 1CBPF/IFUSP, Rio de Janeiro, Brazil, 2Associated Plasma Laboratory, National Space Research Institute, São José dos Campos, SP, Brazil, 3Institute of Plasma Physics, CAS, Hefei, 230031, P.R. China, 4Leabrook Computing, Bournemouth, UK, 5EURATOM/UKAEA Fusion Association, Culham Science Centre, Abingdon, UK, 6TRINITI, Troitsk, RF, 7RRC “Kurchatov Institute”, Moscow, RF [email protected] Abstract An important milestone on the Fast Track path to Fusion Power is to demonstrate reliable commercial application of Fusion as soon as possible. Many applications of fusion, other than electricity production, have already been studied in some depth for ITER class facilities. We show that these applications might be usefully realized on a small scale, in a Multi-Functional Compact Tokamak Reactor based on a Spherical Tokamak with similar size, but higher fields and currents than the present experiments NSTX and MAST, where performance has already exceeded expectations. The small power outputs, 20-40MW, permit existing materials and technologies to be used. The analysis of the performance of the compact reactor is based on the solution of the global power balance using empirical scaling laws considering requirements for the minimum necessary fusion power (which is determined by the optimized efficiency of the blanket design), positive power gain and constraints on the wall load. In addition, ASTRA and DINA simulations have been performed for the range of the design parameters. -
Sixth National Report for the Joint Convention on the Safety of Spent Fuel Management and on the Safety of Radioactive Waste Management
October 2017 United States of America Sixth National Report for the Joint Convention on the Safety of Spent Fuel Management and on the Safety of Radioactive Waste Management U.S. Department of Energy In Cooperation with the U.S. Nuclear Regulatory Commission U.S. Environmental Protection Agency U.S. Department of State This page intentionally left blank. U.S. Sixth National Report-Joint Convention on the Safety of Spent Fuel Management and on the Safety of Radioactive Waste Management ABSTRACT AND ACKNOWLEDGEMENT The United States of America (U.S.) ratified the Joint Convention on the Safety of Spent Fuel Management and on the Safety of Radioactive Waste Management (Joint Convention) on April 9, 2003. The Joint Convention establishes an international peer review process among Contracting Parties and provides incentives for nations to take appropriate steps to bring their spent fuel and radioactive waste management activities into compliance with general safety standards and practices. The U.S. participated in Review Meetings of the Contracting Parties to the Joint Convention in November 2003, May 2006, May 2009, May 2012 and May 2015 in Vienna, Austria. This Sixth National Report, an update of the U.S. Fifth National Report prepared under the Joint Convention in September 2014, documents spent fuel and radioactive waste management safety in the U.S. under the terms of the Joint Convention. The U.S. Government prepared this report for review by the Contracting Parties. The U.S. complies with the terms of the Joint Convention. An extensive U.S. legal and regulatory structure ensures the safety of spent fuel and radioactive waste management. -
小型飛翔体/海外 [Format 2] Technical Catalog Category
小型飛翔体/海外 [Format 2] Technical Catalog Category Airborne contamination sensor Title Depth Evaluation of Entrained Products (DEEP) Proposed by Create Technologies Ltd & Costain Group PLC 1.DEEP is a sensor analysis software for analysing contamination. DEEP can distinguish between surface contamination and internal / absorbed contamination. The software measures contamination depth by analysing distortions in the gamma spectrum. The method can be applied to data gathered using any spectrometer. Because DEEP provides a means of discriminating surface contamination from other radiation sources, DEEP can be used to provide an estimate of surface contamination without physical sampling. DEEP is a real-time method which enables the user to generate a large number of rapid contamination assessments- this data is complementary to physical samples, providing a sound basis for extrapolation from point samples. It also helps identify anomalies enabling targeted sampling startegies. DEEP is compatible with small airborne spectrometer/ processor combinations, such as that proposed by the ARM-U project – please refer to the ARM-U proposal for more details of the air vehicle. Figure 1: DEEP system core components are small, light, low power and can be integrated via USB, serial or Ethernet interfaces. 小型飛翔体/海外 Figure 2: DEEP prototype software 2.Past experience (plants in Japan, overseas plant, applications in other industries, etc) Create technologies is a specialist R&D firm with a focus on imaging and sensing in the nuclear industry. Createc has developed and delivered several novel nuclear technologies, including the N-Visage gamma camera system. Costainis a leading UK construction and civil engineering firm with almost 150 years of history. -
NUCLEAR Unwasted NUCLEAR Unwasted NEWS
N ational Conference of State Legislatures NUCLEAR unWASTEd NEWS A QUARTERLY S UMMARY OF GENERATION, TRANSPORTATION, STORAGE AND DISPOSAL ISSUES JANUARY - MARCH 2008 V OL. 3, NO . 1 Headline CRS Report Assesses Global Access to Nuclear Power 2/29 With the heralding of a coming nuclear renaissance in the Energy Policy Act of 2005 and the Bush administration’s Global Nuclear Energy Partnership (GNEP), the Congressional Research Service released a report in January titled, Managing the Nuclear Fuel Cycle: Policy Implications of Expanding Global Access to Nuclear Power. The 2005 Energy Policy Act outlined provisions authorizing streamlined licensing for new nuclear plants, combining construction and operating permits, and providing tax credits for nuclear power. Thirty new applications or early site permits for reactors have been filed with the Nuclear Regulatory Commission, and 150 have been planned or proposed globally. Nearly a dozen are already under construction overseas. With the U.S. Department of Energy (DOE) planning to spend billions of dollars to advance nuclear technology in the U.S., other countries have similar ideas and want access to the benefits of nuclear power. Advances in nuclear technologies are attractive to those who seek to add energy options to the mostly fossil fuel genera- tion the world depends on today. Concerns about climate change, however, are complicated by fears that spreading enrichment and reprocessing technologies may lead to proliferation of weapons-grade nuclear material. Proposals of global access to nuclear power range from: offering countries access to nuclear power with a formal commit- ment to abstain from enrichment and reprocessing; to a de facto approach where a country does not operate fuel cycle facilities but makes no direct commitment to other nations; to nations having no restrictions at all. -
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. -
Depleted Uranium Technical Brief
Disclaimer - For assistance accessing this document or additional information,please contact [email protected]. Depleted Uranium Technical Brief United States Office of Air and Radiation EPA-402-R-06-011 Environmental Protection Agency Washington, DC 20460 December 2006 Depleted Uranium Technical Brief EPA 402-R-06-011 December 2006 Project Officer Brian Littleton U.S. Environmental Protection Agency Office of Radiation and Indoor Air Radiation Protection Division ii iii FOREWARD The Depleted Uranium Technical Brief is designed to convey available information and knowledge about depleted uranium to EPA Remedial Project Managers, On-Scene Coordinators, contractors, and other Agency managers involved with the remediation of sites contaminated with this material. It addresses relative questions regarding the chemical and radiological health concerns involved with depleted uranium in the environment. This technical brief was developed to address the common misconception that depleted uranium represents only a radiological health hazard. It provides accepted data and references to additional sources for both the radiological and chemical characteristics, health risk as well as references for both the monitoring and measurement and applicable treatment techniques for depleted uranium. Please Note: This document has been changed from the original publication dated December 2006. This version corrects references in Appendix 1 that improperly identified the content of Appendix 3 and Appendix 4. The document also clarifies the content of Appendix 4. iv Acknowledgments This technical bulletin is based, in part, on an engineering bulletin that was prepared by the U.S. Environmental Protection Agency, Office of Radiation and Indoor Air (ORIA), with the assistance of Trinity Engineering Associates, Inc. -
Ards for the Uranium Fuel Cycle PART 191—ENVIRONMENTAL RADI
§ 190.10 40 CFR Ch. I (7–1–11 Edition) period in which he is engaged in car- ance, and the schedule for achieving rying out any operation which is part conformance with the standards. of a nuclear fuel cycle. (l) Regulatory agency means the gov- § 190.12 Effective date. ernment agency responsible for issuing (a) The standards in § 190.10(a) shall regulations governing the use of be effective December 1, 1979, except sources of radiation or radioactive ma- that for doses arising from operations terials or emissions therefrom and car- associated with the milling of uranium rying out inspection and enforcement ore the effective date shall be Decem- activities to assure compliance with ber 1, 1980. such regulations. (b) The standards in § 190.10(b) shall be effective December 1, 1979, except Subpart B—Environmental Stand- that the standards for krypton-85 and ards for the Uranium Fuel iodine-129 shall be effective January 1, Cycle 1983, for any such radioactive materials generated by the fission process after § 190.10 Standards for normal oper- these dates. ations. Operations covered by this subpart PART 191—ENVIRONMENTAL RADI- shall be conducted in such a manner as ATION PROTECTION STANDARDS to provide reasonable assurance that: FOR MANAGEMENT AND DIS- (a) The annual dose equivalent does POSAL OF SPENT NUCLEAR FUEL, not exceed 25 millirems to the whole body, 75 millirems to the thyroid, and HIGH-LEVEL AND TRANSURANIC 25 millirems to any other organ of any RADIOACTIVE WASTES member of the public as the result of exposures to planned discharges of ra- Subpart A—Environmental Standards for dioactive materials, radon and its Management and Storage daughters excepted, to the general en- Sec. -
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.