Getting to the Core of the NUCLEAR FUEL CYCLE
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Table 2.Iii.1. Fissionable Isotopes1
FISSIONABLE ISOTOPES Charles P. Blair Last revised: 2012 “While several isotopes are theoretically fissionable, RANNSAD defines fissionable isotopes as either uranium-233 or 235; plutonium 238, 239, 240, 241, or 242, or Americium-241. See, Ackerman, Asal, Bale, Blair and Rethemeyer, Anatomizing Radiological and Nuclear Non-State Adversaries: Identifying the Adversary, p. 99-101, footnote #10, TABLE 2.III.1. FISSIONABLE ISOTOPES1 Isotope Availability Possible Fission Bare Critical Weapon-types mass2 Uranium-233 MEDIUM: DOE reportedly stores Gun-type or implosion-type 15 kg more than one metric ton of U- 233.3 Uranium-235 HIGH: As of 2007, 1700 metric Gun-type or implosion-type 50 kg tons of HEU existed globally, in both civilian and military stocks.4 Plutonium- HIGH: A separated global stock of Implosion 10 kg 238 plutonium, both civilian and military, of over 500 tons.5 Implosion 10 kg Plutonium- Produced in military and civilian 239 reactor fuels. Typically, reactor Plutonium- grade plutonium (RGP) consists Implosion 40 kg 240 of roughly 60 percent plutonium- Plutonium- 239, 25 percent plutonium-240, Implosion 10-13 kg nine percent plutonium-241, five 241 percent plutonium-242 and one Plutonium- percent plutonium-2386 (these Implosion 89 -100 kg 242 percentages are influenced by how long the fuel is irradiated in the reactor).7 1 This table is drawn, in part, from Charles P. Blair, “Jihadists and Nuclear Weapons,” in Gary A. Ackerman and Jeremy Tamsett, ed., Jihadists and Weapons of Mass Destruction: A Growing Threat (New York: Taylor and Francis, 2009), pp. 196-197. See also, David Albright N 2 “Bare critical mass” refers to the absence of an initiator or a reflector. -
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. -
In Situ Leach (ISL) Mining of Uranium
In Situ Leach (ISL) Mining of Uranium (June 2009) l Most uranium mining in the USA and Kazakhstan is now by in situ leach methods, also known as in situ recovery (ISR). l In USA ISL is seen as the most cost effective and environmentally acceptable method of mining, and Australian experience supports this. l Australia's first ISL uranium mine is Beverley, which started operation late in 2000. The proposal for Honeymoon has government approval and it is expected to be operating in 2008. Conventional mining involves removing mineralised rock (ore) from the ground, breaking it up and treating it to remove the minerals being sought. In situ leaching (ISL), also known as solution mining, or in situ recovery (ISR) in North America, involves leaving the ore where it is in the ground, and recovering the minerals from it by dissolving them and pumping the pregnant solution to the surface where the minerals can be recovered. Consequently there is little surface disturbance and no tailings or waste rock generated. However, the orebody needs to be permeable to the liquids used, and located so that they do not contaminate ground water away from the orebody. Uranium ISL uses the native groundwater in the orebody which is fortified with a complexing agent and in most cases an oxidant. It is then pumped through the underground orebody to recover the minerals in it by leaching. Once the pregnant solution is returned to the surface, the uranium is recovered in much the same way as in any other uranium plant (mill). In Australian ISL mines (Beverley and the soon to be opened Honeymoon Mine) the oxidant used is hydrogen peroxide and the complexing agent sulfuric acid. -
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. -
Per-10 Basic Information Relating to Uranium
PER-10 1 BASIC INFORMATION RELATING TO URANIUM-ENRICHMENT CALCULATIONS AND FUEL REQUIREMENTS FOR NUCLEAR POWER REACTORS by K.T. Brown m 3 ATOMIC ENERGY BOARD Pelindaba PRETORIA Republic of South Africa February 1977 :::: : =:::""""""::::::;::: i:::""""""" :::::::::i:::::::::::::::H:::""»"""::::::::::::::::: BASIC INFORMATION RELATING TO URANIUM-ENRICHMENT CALCULATIONS AND FUEL REQUIREMENTS FOR NUCLEAR POWER REACTORS hy K.T. Brown POSTAL ADDRESS: Atomic Energy Board Private Bag X256 PRETORIA 0001 PELINDABA Fi-ln liai v 1977 ISBN U 86Ü6U 654 9 Pago Page SAMEVATTING 2 ABSTRACT 2 3. REACTOR FUEL REQUIREMENTS 5 1. INTRODUCTION 3 3.1 Reactor Types 5 2. URANIUM ENRICHMENT 3 3.1.1 Pressurised-water roactor 5 2.1 Definitions 3 3.1.2 Boiling-water reactor 5 2.1.1 Natural uranium 3 3.1.3 CANDU-PHW 6 2.1.2 Fissile 3 3.1.4 High-temperature gas-cooled reactor 6 2.1.3 Fertile 3 2.1.5 Liquid-metal-cooled fast breeder reactor ... .6 2.1.4 Enrichment 3 3.2 Nuclear Fuel Cycles 6 2.1.5 Product 3 3.3 Typical Fuel Requirements 6 2.1.6 Feed 3 3.3.1 Pressurised-wator reactor 7 2.1.7 Tails, or waste 3 3.3.2 Boiling-water reactor 8 2.1.8 Cascade 3 3.3.3 CANDU-PHW 9 2.1.9 Separative work 4 3.3.4 High-temperature gas-cooled reactor 9 2.1.10 Separative-work unit 4 3.3.5 Liquid-metal-cooled fast breeder reactor ... 10 2.2 Enrichment Parameters 4 3.3.6 Comparative data 10 2.3 Optimum Tails Assay 5 4. -
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. -
Nuclear Power Reactors in California
Nuclear Power Reactors in California As of mid-2012, California had one operating nuclear power plant, the Diablo Canyon Nuclear Power Plant near San Luis Obispo. Pacific Gas and Electric Company (PG&E) owns the Diablo Canyon Nuclear Power Plant, which consists of two units. Unit 1 is a 1,073 megawatt (MW) Pressurized Water Reactor (PWR) which began commercial operation in May 1985, while Unit 2 is a 1,087 MW PWR, which began commercial operation in March 1986. Diablo Canyon's operation license expires in 2024 and 2025 respectively. California currently hosts three commercial nuclear power facilities in various stages of decommissioning.1 Under all NRC operating licenses, once a nuclear plant ceases reactor operations, it must be decommissioned. Decommissioning is defined by federal regulation (10 CFR 50.2) as the safe removal of a facility from service along with the reduction of residual radioactivity to a level that permits termination of the NRC operating license. In preparation for a plant’s eventual decommissioning, all nuclear plant owners must maintain trust funds while the plants are in operation to ensure sufficient amounts will be available to decommission their facilities and manage the spent nuclear fuel.2 Spent fuel can either be reprocessed to recover usable uranium and plutonium, or it can be managed as a waste for long-term ultimate disposal. Since fuel re-processing is not commercially available in the United States, spent fuel is typically being held in temporary storage at reactor sites until a permanent long-term waste disposal option becomes available.3 In 1976, the state of California placed a moratorium on the construction and licensing of new nuclear fission reactors until the federal government implements a solution to radioactive waste disposal. -
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. -
Understanding Fluid–Rock Interactions and Lixiviant/Oxidant Behaviour for the In-Situ Recovery of Metals from Deep Ore Bodies
School of Earth and Planetary Science Department of Applied Geology Understanding Fluid–Rock Interactions and Lixiviant/Oxidant Behaviour for the In-situ Recovery of Metals from Deep Ore Bodies Tania Marcela Hidalgo Rosero This thesis is presented for the degree of Doctor of Philosophy of Curtin University February 2020 1 Declaration __________________________________________________________________________ Declaration To the best of my knowledge and belief, I declare that this work of thesis contains no material published by any other person, except where due acknowledgements have been made. This thesis contains no material which has been accepted for the award of any other degree or diploma in any university. Tania Marcela Hidalgo Rosero Date: 28/01/2020 2 Abstract __________________________________________________________________________ Abstract In-situ recovery (ISR) processing has been recognised as a possible alternative to open- pit mining, especially for low-grade resources. In ISR, the fluid–rock interaction between the target ore and the lixiviant results in valuable- (and gangue-) metal dissolution. This interaction is achieved by the injection and recovery of fluid by means of strategically positioned wells. Although the application of ISR has become more common (ISR remains the preferential processing technique for uranium and has been applied in pilot programs for treating oxide zones in copper deposits), its application to hard-rock refractory and low-grade copper-sulfide deposits is still under development. This research is focused on the possible application of ISR to primary copper sulfides usually found as deep ores. Lixiviant/oxidant selection is an important aspect to consider during planning and operation in the ISR of copper-sulfide ores. -
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. -
Policy Brief Organisation for Economic Co-Operation and Development
OCTOBER 2008Policy Brief ORGANISATION FOR ECONOMIC CO-OPERATION AND DEVELOPMENT Nuclear Energy Today Can nuclear Introduction energy help make Nuclear energy has been used to produce electricity for more than half a development century. It currently provides about 15% of the world’s supply and 22% in OECD sustainable? countries. The oil crisis of the early 1970s provoked a surge in nuclear power plant orders How safe is and construction, but as oil prices stabilised and even dropped, and enough nuclear energy? electricity generating plants came into service to meet demand, orders tailed off. Accidents at Three Mile Island in the United States (1979) and at Chernobyl How best to deal in Ukraine (1986) also raised serious questions in the public mind about nuclear with radioactive safety. waste? Now nuclear energy is back in the spotlight as many countries reassess their energy policies in the light of concerns about future reliance on fossil fuels What is the future and ageing energy generation facilities. Oil, coal and gas currently provide of nuclear energy? around two-thirds of the world’s energy and electricity, but also produce the greenhouse gases largely responsible for global warming. At the same For further time, world energy demand is expected to rise sharply in the next 50 years, information presenting all societies worldwide with a real challenge: how to provide the energy needed to fuel economic growth and improve social development while For further reading simultaneously addressing environmental protection issues. Recent oil price hikes, blackouts in North America and Europe and severe weather events have Where to contact us? also focused attention on issues such as long-term price stability, the security of energy supply and sustainable development. -
Uranium Fact Sheet
Fact Sheet Adopted: December 2018 Health Physics Society Specialists in Radiation Safety 1 Uranium What is uranium? Uranium is a naturally occurring metallic element that has been present in the Earth’s crust since formation of the planet. Like many other minerals, uranium was deposited on land by volcanic action, dissolved by rainfall, and in some places, carried into underground formations. In some cases, geochemical conditions resulted in its concentration into “ore bodies.” Uranium is a common element in Earth’s crust (soil, rock) and in seawater and groundwater. Uranium has 92 protons in its nucleus. The isotope2 238U has 146 neutrons, for a total atomic weight of approximately 238, making it the highest atomic weight of any naturally occurring element. It is not the most dense of elements, but its density is almost twice that of lead. Uranium is radioactive and in nature has three primary isotopes with different numbers of neutrons. Natural uranium, 238U, constitutes over 99% of the total mass or weight, with 0.72% 235U, and a very small amount of 234U. An unstable nucleus that emits some form of radiation is defined as radioactive. The emitted radiation is called radioactivity, which in this case is ionizing radiation—meaning it can interact with other atoms to create charged atoms known as ions. Uranium emits alpha particles, which are ejected from the nucleus of the unstable uranium atom. When an atom emits radiation such as alpha or beta particles or photons such as x rays or gamma rays, the material is said to be undergoing radioactive decay (also called radioactive transformation).