Advanced Nuclear Reactors: Technology Overview and Current Issues
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Spent Nuclear Fuel Pools in the US
Spent Nuclear Fuel Pools in the U.S.: Reducing the Deadly Risks of Storage front cover WITH SUPPORT FROM: WITH SUPPORT FROM: By Robert Alvarez 1112 16th St. NW, Suite 600, Washington DC 20036 - www.ips-dc.org May 2011 About the Author Robert Alvarez, an Institute for Policy Studies senior scholar, served as a Senior Policy Advisor to the Secre- tary of Energy during the Clinton administration. Institute for Policy Studies (IPS-DC.org) is a community of public scholars and organizers linking peace, justice, and the environment in the U.S. and globally. We work with social movements to promote true democracy and challenge concentrated wealth, corporate influence, and military power. Project On Government Oversight (POGO.org) was founded in 1981 as an independent nonprofit that investigates and exposes corruption and other misconduct in order to achieve a more effective, accountable, open, and ethical federal government. Institute for Policy Studies 1112 16th St. NW, Suite 600 Washington, DC 20036 http://www.ips-dc.org © 2011 Institute for Policy Studies [email protected] For additional copies of this report, see www.ips-dc.org Table of Contents Summary ...............................................................................................................................1 Introduction ..........................................................................................................................4 Figure 1: Explosion Sequence at Reactor No. 3 ........................................................4 Figure 2: Reactor No. 3 -
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. -
IAEA Guidelines and Formatting Rules for Papers for Proceeding
Interactive Computer Codes for Education and Training on Nuclear Safety and Radioprotection Francisco leszczynski∗ RA-6 Division, Nuclear Engineering Unit, Bariloche Atomic Center, CNEA, Av.E.Bustillo 8500, S.C.de Bariloche, RN, Argentina Abstract. Two interactive computer codes for education and training on nuclear safety and radioprotection developed at RA6 Reactor Division-Bariloche Atomic Center-CNEA are presented on this paper. The first code named SIMREACT has been developed in order to simulate the control of a research nuclear reactor in real time with a simple but accurate approach. The code solves the equations of neutron punctual kinetics with time variable reactivity. Utilizing the timer of the computer and the controls of a PC keyboard, with an adequate graphic interface, a simulation in real time of the temporal behavior of a research reactor is obtained. The reactivity can be changed by means of the extraction or insertion of control rods. It was implemented also the simulation of automatic pilot and scram. The use of this code is focalized on practices of nuclear reactor control like start-up from the subcritical state with external source up to power to a desired level, change of power level, calibration of a control rod with different methods, and approach to critical condition by interpolation of the answer in function of reactivity. The second code named LICEN has been developed in order to help the studies of all the topics included in examination programs for obtaining licenses for research reactor operators and radioprotection officials. Using the PC mouse, with an adequate graphic interface, the student can gradually learn the topics related with general and special licenses. -
Materials and Fuels Testing Techniques in the Advanced Test Reactor – from Simple to Complex
Materials and Fuels Testing Techniques in the Advanced Test Reactor – From Simple to Complex Raymond V. Furstenau 1), Frederick W. Ingram 2), John E. Brasier 2), Mark B. Hendrickson 2) 1) Idaho National Engineering and Environmental Laboratory, U.S. Dept. of Energy, USA 2) Idaho National Engineering and Environmental Laboratory, Bechtel BWXT Idaho, USA ABSTRACT The Advanced Test Reactor (ATR) is the third generation of test reactors built at the Test Reactor Area (TRA), Idaho National Engineering and Environmental Laboratory (INEEL), to study the effects of intense neutron and gamma radiation on reactor materials and fuels. ATR has a maximum power of 250MW and can provide maximum thermal neutron fluxes of 1E15 neutrons per square centimeter per second. This allows considerable acceleration of accumulated neutron fluence to materials and fuels over what would be seen in a typical power reactor. Since power operation of the ATR began in 1969, numerous testing methods have been developed to take advantage of the capabilities of the ATR. The wide range of experiment facilities in the ATR and the unique ability to vary the neutron flux in different areas of the core allow numerous experiment conditions to co-exist during the same reactor operating cycle. Simple experiments may involve a non- instrumented sealed capsule containing test specimens with no real-time monitoring and control capabilities. The Irradiation Test Vehicle, installed in 1999, is the newest testing apparatus in the ATR that accommodates up to fifteen separate tests, each with its own temperature control and monitoring capabilities as well as neutron spectral tailoring capability. More sophisticated testing facilities include pressurized water loops that have continuous chemistry, pressure, temperature, and flow control as well as numerous test specimen monitoring capabilities. -
Nuclear Energy: Fission and Fusion
CHAPTER 5 NUCLEAR ENERGY: FISSION AND FUSION Many of the technologies that will help us to meet the new air quality standards in America can also help to address climate change. President Bill Clinton 1 Two distinct processes involving the nuclei of atoms can be harnessed, in principle, for energy production: fission—the splitting of a nucleus—and fusion—the joining together of two nuclei. For any given mass or volume of fuel, nuclear processes generate more energy than can be produced through any other fuel-based approach. Another attractive feature of these energy-producing reactions is that they do not produce greenhouse gases (GHG) or other forms of air pollution directly. In the case of nuclear fission—a mature though controversial energy technology—electricity is generated from the energy released when heavy nuclei break apart. In the case of nuclear fusion, much work remains in the quest to sustain the fusion reactions and then to design and build practical fusion power plants. Fusion’s fuel is abundant, namely, light atoms such as the isotopes of hydrogen, and essentially limitless. The most optimistic timetable for fusion development is half a century, because of the extraordinary scientific and engineering challenges involved, but fusion’s benefits are so globally attractive that fusion R&D is an important component of today’s energy R&D portfolio internationally. Fission power currently provides about 17 percent of the world’s electric power. As of December 1996, 442 nuclear power reactors were operating in 30 countries, and 36 more plants were under construction. If fossil plants were used to produce the amount of electricity generated by these nuclear plants, more than an additional 300 million metric tons of carbon would be emitted each year. -
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 -
Radionuclide Concentrations in Air on the Hanford Site
PNNL-13909 Radionuclide Concentrations in Air on the Hanford Site A Ten-Year Trend Report 1991 Through 2000 B. G. Fritz G. W. Patton May 2002 Prepared for the U.S. Department of Energy under Contract DE-AC06-76RL01830 DISCLAIMER This report was prepared as an account of work sponsored by an agency of the United States Government. Neither the United States Government nor any agency thereof, nor Battelle Memorial Institute, nor any of their employees, makes any warranty, express or implied, or assumes any legal liability or responsibility for the accuracy, completeness, or usefulness of any information, apparatus, product, or process disclosed, or represents that its use would not infringe privately owned rights. Reference herein to any specific commercial product, process, or service by trade name, trademark, manufacturer, or otherwise does not necessarily constitute or imply its endorsement, recommendation, or favoring by the United States Government or any agency thereof, or Battelle Memorial Institute. The views and opinions of authors expressed herein do not necessarily state or reflect those of the United States Government or any agency thereof. PACIFIC NORTHWEST NATIONAL LABORATORY operated by BATTELLE for the UNITED STATES DEPARTMENT OF ENERGY under Contract DE-AC06-76RL01830 This document was printed on recycled paper. (8/00) PNNL-13909 Radionuclide Concentrations in Air on the Hanford Site A Ten-Year Trend Report 1991 through 2000 B. G. Fritz G. W. Patton May 2002 Prepared for the U.S. Department of Energy under Contract DE-AC06-76RL01830 Pacific Northwest National Laboratory Richland, Washington 99352 Summary This report describes the air pathway effects of Hanford Site operations from 1991 through 2000 on local air quality. -
Arxiv:2003.07462V2 [Cond-Mat.Mtrl-Sci] 8 Jun 2020
The Structure of Molten FLiNaK Benjamin A. Frandsena,∗, Stella D. Nickersonb, Austin D. Clarkb, Andrew Solanob, Raju Barala, Jonathan Williamsb, J¨orgNeuefeindc, Matthew Memmottb aDepartment of Physics and Astronomy, Brigham Young University, Provo, Utah 84602, USA. bDepartment of Chemical Engineering, Brigham Young University, Provo, Utah 84602, USA. cNeutron Scattering Division, Oak Ridge National Laboratory, Oak Ridge, Tennessee 37831, USA. Abstract The structure of the molten salt (LiF)0:465(NaF)0:115(KF)0:42 (FLiNaK), a potential coolant for molten salt nuclear reactors, has been studied by ab initio molecular dynamics simulations and neutron total scattering experiments. We find that the salt retains well-defined short-range structural correlations out to approximately 9 A˚ at typical reactor operating temperatures. The experimentally determined pair distribution function can be described with quantitative accuracy by the molecular dynamics simulations. These results indicate that the essential ionic interactions are properly captured by the simulations, providing a launching point for future studies of FLiNaK and other molten salts for nuclear reactor applications.1 Keywords: molten salt reactor, FLiNaK, total scattering, pair distribution function, molecular dynamics Molten salt reactors (MSRs) are a promising nuclear reactor concept in which fuel and/or fertile material are dissolved directly into a halide salt coolant. This has significant benefits over traditional light water reactors (LWRs) that are in operation today, including the capability of producing medical radioisotopes and electricity simultane- ously in large amounts [1] and the possibility of reactor designs that prevent proliferation of weaponizable material, eliminate the risk of meltdown events, and avoid producing long-lived transuranic nuclear waste [2, 3]. -
Small Modular Reactor Design and Deployment
INL/MIS-15-34247 Small Modular Reactor Design and Deployment Curtis Wright Symposium xx/xx/xxxx www.inl.gov INL SMR Activities • INL works with all vendors to provide fair access to the laboratory benefits • INL works with industry on SMR technology and deployment • INL is supporting multiple LWR SMR vendors – Small, <300MWe reactors and less expensive reactors compared to current LWR reactors (Small) – Often, but not always, multiple reactors at the same site that can be deployed as power is needed (Modular) – Primary cooling system and reactor core in a single containment structure, but not always (Reactors) – Factory built, usually, which improves quality and costs • Integrated PWR SMR’s are closest to deployment – designed to be inherently safer and simple – primary reactor system inside a single factory built containment vessel – Higher dependence on passive systems to simplify operation and design Reactor Power Nuclear Plant Power Los Angeles Class Submarine -26 MW 5000 Enterprise Class Aircraft Carrier 8x 4000 Unit Power Nimitz Class Aircraft Carrier 2x97MW, 194MW 3000 Plant Power NuScale Reactor 12 x 150MW, 1800MW 2000 Cooper BWR, 1743MW PowerThermal MW 1000 Westinghouse AP-1000, 3000MW 0 European Pressurized Reactor, 4953MW SMRs are Smaller VC Summer • Power less than 300MWe. Dearater – Current Plants 1000MWe – Physically smaller – Fewer inputs – Fits on power grid with less infrastructure – Built in a factory – Simplified designs VC Summer • Passive systems Core • Fewer components NuScale Reactor Multiple Units • SMR Nuclear -
Preparing for Nuclear Waste Transportation
Preparing for Nuclear Waste Transportation Technical Issues that Need to Be Addressed in Preparing for a Nationwide Effort to Transport Spent Nuclear Fuel and High-Level Radioactive Waste A Report to the U.S. Congress and the Secretary of Energy September 2019 U.S. Nuclear Waste Technical Review Board This page intentionally left blank. U.S. Nuclear Waste Technical Review Board Preparing for Nuclear Waste Transportation Technical Issues That Need to Be Addressed in Preparing for a Nationwide Effort to Transport Spent Nuclear Fuel and High-Level Radioactive Waste A Report to the U.S. Congress and the Secretary of Energy September 2019 This page intentionally left blank. U.S. Nuclear Waste Technical Review Board Jean M. Bahr, Ph.D., Chair University of Wisconsin, Madison, Wisconsin Steven M. Becker, Ph.D. Old Dominion University, Norfolk, Virginia Susan L. Brantley, Ph.D. Pennsylvania State University, University Park, Pennsylvania Allen G. Croff, Nuclear Engineer, M.B.A. Vanderbilt University, Nashville, Tennessee Efi Foufoula-Georgiou, Ph.D. University of California Irvine, Irvine, California Tissa Illangasekare, Ph.D., P.E. Colorado School of Mines, Golden, Colorado Kenneth Lee Peddicord, Ph.D., P.E. Texas A&M University, College Station, Texas Paul J. Turinsky, Ph.D. North Carolina State University, Raleigh, North Carolina Mary Lou Zoback, Ph.D. Stanford University, Stanford, California Note: Dr. Linda Nozick of Cornell University served as a Board member from July 28, 2011, to May 9, 2019. During that time, Dr. Nozick provided valuable contributions to this report. iii This page intentionally left blank. U.S. Nuclear Waste Technical Review Board Staff Executive Staff Nigel Mote Executive Director Neysa Slater-Chandler Director of Administration Senior Professional Staff* Bret W. -
Molten Salts As Blanket Fluids in Controlled Fusion Reactors [Disc 6]
r1 0 R N L-TM-4047 MOLTEN SALTS AS BLANKET FLUIDS IN CONTROLLED FUSION REACTORS W. R. Grimes Stanley Cantor .:, .:, .- t. This report was prepared as an account of work sponsored by the United States Government. Neither the United States nor the United States Atomic Energy Commission, nor any of their employees, nor any of their contractors, subcontractors, or their employees, makes any warranty, express or implied, or assumes any legal liability or responsibility for the accuracy, completeness or usefulness of any information, apparatus, product or process disclosed, or represents that its use would not infringe privately owned rights. om-TM- 4047 Contract No. W-7405-eng-26 REACTOR CHENISTRY DIVISION MOLTEN SALTS AS BLANKET FLUIDS IN CONTROLLED FUSION REACTORS W. R. Grimes and Stanley Cantor DECEMBER 1972 OAK RIDGE NATIONAL LABORATORY Oak Ridge, Tennessee 37830 operated by UNION CARBIDE CORPORATION for the 1J.S. ATOMIC ENERGY COMMISSION This report was prepared as an account of work sponsored by the United States Government. Neither the United States nor the United States Atomic Energy Commission, nor any of their employees, nor any of their contractors, subcontractors, or their employees, makes any warranty, express or implied, or assumes any legal liability or responsibility for the accuracy, com- pleteness or usefulness of any information, apparatus, product or process disclosed, or represents that its use would not infringe privately owned rights. i iii CONTENTS Page Abstract ............................. 1 Introduction ........................... 2 Behavior of Li2BeFq in a Eypothetical CTR ............3 Effects of Strong Magnetic Fields .............5 Effects on Chemical Stability .............5 Effects on Fluid Dynamics ...............7 Production of Tritium .................. -
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.