RETHINKING the CHALLENGE of HIGH-LEVEL NUCLEAR WASTE Strategic Planning for Defense High-Level Waste and Spent Fuel 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. -
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. -
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. -
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. -
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. -
5. Production, Import/Export, Use, and Disposal
IODINE 227 5. PRODUCTION, IMPORT/EXPORT, USE, AND DISPOSAL 5.1 PRODUCTION Iodine, a halogen, occurs in low concentrations in nature in the form of iodides mainly in sea water, although there are a number of major sources iodine including the underground waters from certain deep- well boring and mineral springs (i.e., brines) and natural deposits of sodium nitrate ore (i.e., caliche) found in the northern part of Chile. Only a few marine organisms contain iodine in relatively large quantities including seaweeds, sponges, and corals. The different production processes for recovering iodine are based on the raw materials used. Approximately 54% of the iodine consumed in the world is obtained from Chile as a coproduct from surface mineral deposits used to produce nitrate fertilizers (USGS 2002). About 43% of the iodine consumed in the world comes from brines processed in Japan, the United States, and the former Soviet Union. The primary production process for recovery of iodine from brines is the blow-out process. The blow-out process for brines can be divided into brine clean-up, iodide oxidation followed by air blowing and recovery, and iodine finishing. In 2001, iodine was recovered from brines by the blow-out process by three companies operating in Oklahoma, which accounted for 100% of the U.S. elemental iodine production. These three companies are IOCHEM Corporation (Dewey County, Oklahoma), North American Brine Resources (Dover, Oklahoma), and Woodward Iodine Corporation (Woodward County, Oklahoma). Production of iodine in the United States has remained steady ranging from 1,270 to 1,620 metric tons between the years 1996 and 2000 (Lauterbach and Ober 1995; USGS 1998, 2002). -
Advanced Reactor and Small Modular Reactor Licensing
Pacific Northwest National Laboratory is managed and operated by Battelle for the U.S. Department of Energy. PNNL Points of Contact: Tara O’Neil Nuclear Regulatory Sub-Sector Manager [email protected] (541) 738-0362 PACIFIC NORTHWEST NATIONAL Bruce McDowell Advanced Reactors Program Manager [email protected] LABORATORY’S EXPERIENCE IN (509) 375-6668 ADVANCED REACTOR AND nuclearenergy.pnnl.gov PNNL-SA-138133 | September 2018 SMALL MODULAR REACTOR LICENSING INFRASTRUCTURE or more than 30 years, • Supported the development of the Next Generation Nuclear Plant (NGNP) High Priority Regulatory Topical the Nuclear Regulatory Reports related to NGNP Licensing (see SECY-10- 0034, Potential Policy, Licensing, And Key Technical Commission has reached Issues for Small Modular Nuclear Reactor Designs). out to Pacific Northwest National • Provided recommendations to NRC on modifications F of health physics codes for SMRs, and to update the Laboratory at critical stages of Gaseous And Liquid Effluent (GALE) codes. nuclear plant design for assistance • Supported development of American Nuclear Society (ANS) 53.1 Nuclear Safety Criteria and Safety Design in developing and applying new Process for Modular Helium-Cooled Reactor Plants, and ASME/ANS S1.4, Standard for Probabilistic Risk standards for safety reviews of Assessment for Advanced Non-Light Water Reactor Nuclear Power Plants. new plant designs. • Prepared “High Temperature Gas Reactors: Assessment of Applicable Codes and Standards” (PNNL-20869, October 2011) in support of NRC’s Advanced -
Fast-Spectrum Reactors Technology Assessment
Clean Power Quadrennial Technology Review 2015 Chapter 4: Advancing Clean Electric Power Technologies Technology Assessments Advanced Plant Technologies Biopower Clean Power Carbon Dioxide Capture and Storage 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 U.S. DEPARTMENT OF Supercritical Carbon Dioxide Brayton Cycle ENERGY Wind Power Clean Power Quadrennial Technology Review 2015 Fast-spectrum Reactors Chapter 4: Technology Assessments Background and Current Status From the initial conception of nuclear energy, it was recognized that full realization of the energy content of uranium would require the development of fast reactors with associated nuclear fuel cycles.1 Thus, fast reactor technology was a key focus in early nuclear programs in the United States and abroad, with the first usable nuclear electricity generated by a fast reactor—Experimental Breeder Reactor I (EBR-I)—in 1951. Test and/or demonstration reactors were built and operated in the United States, France, Japan, United Kingdom, Russia, India, Germany, and China—totaling about 20 reactors with 400 operating years to date. These previous reactors and current projects are summarized in Table 4.H.1.2 Currently operating test reactors include BOR-60 (Russia), Fast Breeder Test Reactor (FBTR) (India), and China Experimental Fast Reactor (CEFR) (China). The Russian BN-600 demonstration reactor has been operating as a power reactor since 1980. -
Advanced Nuclear Power and Fuel Cycle Technologies: Outlook and Policy Options
Order Code RL34579 Advanced Nuclear Power and Fuel Cycle Technologies: Outlook and Policy Options July 11, 2008 Mark Holt Specialist in Energy Policy Resources, Science, and Industry Division Advanced Nuclear Power and Fuel Cycle Technologies: Outlook and Policy Options Summary Current U.S. nuclear energy policy focuses on the near-term construction of improved versions of existing nuclear power plants. All of today’s U.S. nuclear plants are light water reactors (LWRs), which are cooled by ordinary water. Under current policy, the highly radioactive spent nuclear fuel from LWRs is to be permanently disposed of in a deep underground repository. The Bush Administration is also promoting an aggressive U.S. effort to move beyond LWR technology into advanced reactors and fuel cycles. Specifically, the Global Nuclear Energy Partnership (GNEP), under the Department of Energy (DOE) is developing advanced reprocessing (or recycling) technologies to extract plutonium and uranium from spent nuclear fuel, as well as an advanced reactor that could fully destroy long-lived radioactive isotopes. DOE’s Generation IV Nuclear Energy Systems Initiative is developing other advanced reactor technologies that could be safer than LWRs and produce high-temperature heat to make hydrogen. DOE’s advanced nuclear technology programs date back to the early years of the Atomic Energy Commission in the 1940s and 1950s. In particular, it was widely believed that breeder reactors — designed to produce maximum amounts of plutonium from natural uranium — would be necessary for providing sufficient fuel for a large commercial nuclear power industry. Early research was also conducted on a wide variety of other power reactor concepts, some of which are still under active consideration. -
Nuclear-Spent Fuel and High-Level Radioactive Waste Disposal Preface and Acknowledgments 5
Nuclear-Spent Science Matters, LLC Science Matters, Bethesda, Maryland Fuel and High-Level Radioactive December 2019 Waste Disposal A Review of Options Considered in the United States An independent report Deepcommissioned Inc. Isolation, by Arjun Makhijani, Ph.D. Table of Contents Preface and Acknowledgments 4 Executive Summary 8 i. Early considerations 9 ii. The 1980 Environmental Impact Statement and geologic disposal 11 iii. Retrospective on the geologic disposal decision 13 iv. The 1982 Nuclear Waste Policy Act 14 v. The Continued Storage Rule 15 vi. Conclusions 16 I. From the 1950s to the mid-1970s 18 i. The 1957 National Research Council Report 20 ii. Lyons, Kansas 26 II. The changing framework in the 1970s 33 i. The energy front 34 ii. A change in nuclear power prospects 35 iii. The Indian nuclear test 38 III. Options for spent-fuel and high-level waste disposal 41 i. Transmutation 45 ii. Disposal in space 48 iii. Ice-sheet disposal 54 iv. Sub-seabed disposal 58 v. Island disposal 61 vi. Well injection 61 vii. Rock melt 64 viii. Disposal in very deep holes 66 ix. Disposal in a mined geologic repository 69 IV. Retrospective on disposal options 78 i. Breeder reactors and reprocessing 80 ii. Reprocessing-dependent disposal approaches 83 iii. Non-reprocessing dependent disposal concepts 88 iv. Deep-vertical borehole disposal 93 v. Horizontal borehole disposal 95 V. The Nuclear Waste Policy Act 98 VI. The NRC’s Continued Storage Rule and geologic isolation 106 i. The Continued Storage Rule 107 ii. Comments on continued storage and geologic isolation 108 VII. -
Appendix a of Final Environmental Impact Statement for a Geologic Repository for the Disposal of Spent Nuclear Fuel and High-Lev
Appendix A Inventory and Characteristics of Spent Nuclear Fuel, High-Level Radioactive Waste, and Other Materials Inventory and Characteristics of Spent Nuclear Fuel, High-Level Radioactive Waste, and Other Materials TABLE OF CONTENTS Section Page A. Inventory and Characteristics of Spent Nuclear Fuel, High-Level Radioactive Waste, and Other Materials ................................................................................................................................. A-1 A.1 Introduction .............................................................................................................................. A-1 A.1.1 Inventory Data Summary .................................................................................................... A-2 A.1.1.1 Sources ......................................................................................................................... A-2 A.1.1.2 Present Storage and Generation Status ........................................................................ A-4 A.1.1.3 Final Waste Form ......................................................................................................... A-6 A.1.1.4 Waste Characteristics ................................................................................................... A-6 A.1.1.4.1 Mass and Volume ................................................................................................. A-6 A.1.1.4.2 Radionuclide Inventories ...................................................................................... A-8 A.1.1.4.3 -
Regulatory Technology Development Plan Sodium Fast Reactor Mechanistic Source Term – Metal Fuel Radionuclide Release
ANL-ART-38 Regulatory Technology Development Plan Sodium Fast Reactor Mechanistic Source Term – Metal Fuel Radionuclide Release Nuclear Engineering Division About Argonne National Laboratory Argonne is a U.S. Department of Energy laboratory managed by UChicago Argonne, LLC under contract DE-AC02-06CH11357. The Laboratory’s main facility is outside Chicago, at 9700 South Cass Avenue, Argonne, Illinois 60439. For information about Argonne and its pioneering science and technology programs, see www.anl.gov. DOCUMENT AVAILABILITY Online Access: U.S. Department of Energy (DOE) reports produced after 1991 and a growing number of pre-1991 documents are available free via DOE’s SciTech Connect (http://www.osti.gov/scitech/) Reports not in digital format may be purchased by the public from the National Technical Information Service (NTIS): U.S. Department of Commerce National Technical Information Service 5301 Shawnee Rd Alexandria, VA 22312 www.ntis.gov Phone: (800) 553-NTIS (6847) or (703) 605-6000 Fax: (703) 605-6900 Email: [email protected] Reports not in digital format are available to DOE and DOE contractors from the Office of Scientific and Technical Information (OSTI): U.S. Department of Energy Office of Scientific and Technical Information P. O . B o x 6 2 Oak Ridge, TN 37831-0062 www.osti.gov Phone: (865) 576-8401 Fax: (865) 576-5728 Email: [email protected] 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 UChicago Argonne, LLC, nor any of their employees or officers, 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.