DOCSLIB.ORG

NUCLEAR WASTE MANAGEMENT TECHNICAL SUPPORT DOCUMENT NEW NUCLEAR - DARLINGTON ENVIRONMENTAL ASSESSMENT NK054-REP-07730-00027 Rev 000

Total Page：16

File Type：pdf, Size：1020Kb

Download full-text PDF Read full-text
NUCLEAR WASTE MANAGEMENT TECHNICAL SUPPORT DOCUMENT NEW NUCLEAR - DARLINGTON ENVIRONMENTAL ASSESSMENT NK054-REP-07730-00027 Rev 000 NUCLEAR WASTE MANAGEMENT TECHNICAL SUPPORT DOCUMENT NEW NUCLEAR - DARLINGTON ENVIRONMENTAL ASSESSMENT NK054-REP-07730-00027 Rev 000 Prepared By: Nuclear Waste Management Division Ontario Power Generation Inc. August 2009 New Nuclear – Darlington Environmental Assessment Nuclear Waste Management Ontario Power Generation Inc. Technical Support Document EXECUTIVE SUMMARY This Technical Support Document (TSD) relates to Nuclear Waste Management for the New Nuclear – Darlington Project (NND) and has been prepared to support the NND Environmental Assessment. It describes available technologies and assesses the radiological effects on members of the public and Nuclear Energy Workers (NEWs) on the Darlington Nuclear (DN) site from operating the on-site radioactive waste storage systems. It has been prepared by the Nuclear Waste Management Division (NWMD) of Ontario Power Generation Inc. (OPG), which carries technical responsibility for the Nuclear Waste Management System for NND. This TSD is one of a series of related documents describing different aspects of the overall effects assessment, one for each environmental component. More details on the basis for the EA are given in Appendix C. The radioactive low and intermediate level waste (L&ILW) produced during the operation, maintenance, refurbishment, and decommissioning of the reactors will be managed in a similar manner regardless of the reactor design selected. L&ILW will be managed either on the DN site in a L&ILW management facility or transported off-site to be managed at an appropriately licensed facility. On-site used nuclear fuel storage facilities (both wet and dry) will be part of each of the reactor designs considered. The on-site dry storage of used fuel proposed for all three reactor designs is expansion of the current at the Darlington Waste Management Facility (DWMF). It is assumed that the used fuel will be stored on-site until the federally mandated Nuclear Waste Management Organization (NWMO) takes responsibility for the long-term management of the used fuel. It is assumed that the NWMO long-term management facility will be available within the operating lifespan of NND. ES-1 Waste Management Concepts The range of options presented for management of the radioactive wastes that will be generated by the proposed NND is intended to provide bounding conditions for the EA. No decision has yet been taken on which waste management system will be used. The EA will consider two options for storage of low and intermediate level waste (L&ILW): on-site, using compaction, packaging, and a modular storage building; and off-site, transporting un-processed L&ILW to an appropriately licensed facility. Storage is assumed to be in “standard” L&ILW Storage Buildings (SBs). The Atomic Energy of Canada Limited (AECL) MACSTOR (Modular Air Cooled STORage) system is the standard used fuel dry storage (UFDS) system offered by AECL for the proposed reactor ACR-1000, consisting of concrete storage cells that provide shielding and convective air cooling. Another option for the ACR-1000 is OPG’s Dry Storage Container (DSC) system - a proven system that has been used for CANada DeuteriumUranium (CANDU) used fuel since 1995. ES-1 New Nuclear – Darlington Environmental Assessment Nuclear Waste Management Ontario Power Generation Inc. Technical Support Document Three basic technologies are widely used around the world for dry storage of used Pressurized Water Reactor (PWR) fuels: solid metal casks suitable for transport or storage; concrete canisters consisting of an outer vertical concrete shield with an inner steel liner; and concrete modules, consisting of an outer horizontal concrete shield vault with an inner steel liner. Long-term management and eventual disposal of used fuel in Canada is the responsibility of the NWMO. Refurbishment wastes are conservatively assumed to be stored on-site until the stations are decommissioned, at which point they will be transported off-site to a suitably licensed repository. Steam generators may eventually need to be segmented for off-site shipment. The majority of the decommissioning wastes will be generated at the time the station is dismantled. It is assumed that on-site storage of these wastes will not be required and that they will be sent directly to a suitable repository. Long term site planning for NND will need to consider space for three L&ILW SBs (4,500 m2), three UFDS buildings (16,000 m2), one UFDS processing building (2,000 m2), one steam generator storage building (4,550 m2), and one refurbishment waste storage building (3,150 m2). The total area should include a minimum 5 m buffer between the storage buildings and the waste management facility fence, plus an additional buffer for security around the UFDS buildings. While there is no reason to believe that a Safety Assessment could not demonstrate that a location north of the CN rail line is feasible, the safety assessment used in this TSD assume that any waste processing or storage building are built south of the CN rail line and no closer than 150 m to the site perimeter fence. However, for EA planning purposes, this TSD has accepted this analysis to demonstrate that the UFDS can be located anywhere on the site. Should the Vendor require the UFDS buildings to be located north of the CN rail line, or any waste processing or storage building to be located closer than 150 m to the site perimeter fence, OPG has committed to updating safety assessment for this location as part of the licensing process. An EA for the existing DWMF was completed [OPG, 2003] and approved in 2004 for the construction and operation of the processing building for used fuel. The DWMF has been in-service since January 2008. ES-2 Waste Forecasts Operational Wastes will include both L&ILW and used nuclear fuel. L&ILW is assumed to be largely similar to wastes from OPG's current reactor fleet, both in its physical characteristics and in its radiological activity levels. The volumes and types of L&ILW for each reactor are summarized, both annually and the expected lifetime arisings for a nominal 60 years operation: for both the ACR-1000 and AP1000 ES-2 New Nuclear – Darlington Environmental Assessment Nuclear Waste Management Ontario Power Generation Inc. Technical Support Document designs, the expected lifetime arisings are just below 10,000 m3; for the Areva US EPR (EPR) design, approximately 13,500 m3 lifetime arisings are expected. An important “new” waste stream for the AP1000 and Evolutionary Pressurized Reactor (EPR) is related to the boric acid system used for reactivity control in light water reactors. All three reactor technologies under consideration for use at NND use enriched fuel, although the degree of enrichment varies by reactor type. The dimensions and configuration of ACR-1000 fuel is quite similar to conventional CANDU fuel. The fuel used by the AP1000 and EPR are of an entirely different design. The ACR-1000 is operated with on-power refuelling: fuel bundles are discharged in a regular stream to the fuel bay and stored in baskets designed to be compatible with the AECL MACSTOR dry storage system. PWRs are operated in batch cycles of 18 months to 2 years, after which the reactor is shut down and a portion of the core removed and replaced with new fuel. The expected used fuel arisings (in tonnes of uranium over the lifetime) from each of the reactor designs are: ACR-1000, 5,246; AP1000, 1,400; and EPR, 2,712. For refurbishment wastes, this study assumes that mid-life refurbishment will be required. For the ACR-1000, this would consist of replacing the steam generators, fuel channels, calandria tubes, and feeders. For the AP1000 and EPR, refurbishment would consist of replacing the steam generators and reactor vessel heads. ES-3 Waste Management Considerations ES-3.1 Waste Characteristics L&ILW from the light water reactors are expected to have much less tritium and C-14 than the current CANDU reactors. Tritium and C-14 from the ACR-1000 are expected to be comparable to current operations if no tritium removal facility is in operation. An important “new” waste stream to Canadian power reactors is related to the boric acid system used for reactivity control in light water reactors and criticality control in the used fuel bays. The fuel from the new-build reactors will have higher enrichment than current CANDU fuels. This introduces elements of criticality control requirements for storage as well as potential heat load issues for dry storage and eventual disposal. The light water reactor fuel assemblies are much larger and heavier than the traditional CANDU fuel bundle. The steam generators for the reactor types considered are larger and heavier than those used in OPG’s existing reactor fleet, making procedures surrounding their eventual replacement more complex. The radioactivity in a steam generator is expected to be similar for all reactor types. ES-3 New Nuclear – Darlington Environmental Assessment Nuclear Waste Management Ontario Power Generation Inc. Technical Support Document ES-3.2 Processing There are two processing scenarios being considered for LLW in the NND environmental assessment: on-site processing, consisting of compaction and storage; and transport to an off-site facility. On-site processing using compaction will reduce the volume for eventual off-site transportation but is the not the most effective technique to minimize overall storage requirements. Off-site processing can further reduce disposal volumes by the use of more advanced processing technologies at the expense of increased initial transportation. Processing of used fuel refers to preparation for dry storage, which is well-developed both within OPG and internationally. Some modifications to available designs will be required for all reactor types due to the new fuel dimensions and for the ACR-1000 higher burnup and heat load. Refurbishment waste may require decontamination and/or size reduction.
Load more

Recommended publications
  • Nondestructive Examination Guidance for Dry Storage Casks
    PNNL-24412 Rev. 1 Nondestructive Examination Guidance for Dry Storage Casks September 2016 RM Meyer S Suffield EH Hirt JD Suter JP Lareau JW Zhuge A Qiao TL Moran P Ramuhalli PNNL-24412 Rev. 1 Nondestructive Examination Guidance for Dry Storage Casks RM Meyer S Suffield EH Hirt JD Suter JP Lareau JW Zhuge A Qiao TL Moran P Ramuhalli September 2016 Prepared for the U.S. Nuclear Regulatory Commission under a Related Services Agreement with the U.S. Department of Energy Contract DE-AC05-76RL01830 Pacific Northwest National Laboratory Richland, Washington 99352 Abstract This report reviews nondestructive examination (NDE) methods and their applicability to aging effects in concrete overpack and metal canister components to support U.S. Nuclear Regulatory Commission staff with review of renewal applications for welded canister-type dry storage systems (DSSs). In the United States, several DSSs for commercial spent nuclear fuel are approaching the end of their initial licensed or certified term. Many of these systems have originally been licensed or certified for 20 years, after which they may be renewed for periods up to 40 years, according to Title 10 of the Code of Federal Regulations (10 CFR), Part 72, “Licensing Requirements for the Independent Storage of Spent Nuclear Fuel, High- Level Radioactive Waste, and Reactor-Related Greater than Class C Waste.” An analysis of implementation of NDE methods to concrete horizontal storage modules (HSMs) in Transnuclear NUHOMS 80 and 102 DSSs is provided as an example to illustrate factors that should be considered when reviewing NDE methods proposed by applicants for welded canister-type DSSs in general.
    [Show full text]
  • GAO-15-141, SPENT NUCLEAR FUEL MANAGEMENT: Outreach
    United States Government Accountability Office Report to Congressional Requesters October 2014 SPENT NUCLEAR FUEL MANAGEMENT Outreach Needed to Help Gain Public Acceptance for Federal Activities That Address Liability GAO-15-141 D October 2014 SPENT NUCLEAR FUEL MANAGEMENT Outreach Needed to Help Gain Public Acceptance for Federal Activities That Address Liability Highlights of GAO-15-141, a report to congressional requesters Why GAO Did This Study What GAO Found DOE is responsible for disposing of Spent nuclear fuel—the used fuel removed from nuclear power reactors—is commercial spent nuclear fuel. DOE expected to accumulate at an average rate of about 2,200 metric tons per year in entered into contracts with owners and the United States. This spent nuclear fuel is mostly stored wet, submerged in generators of spent nuclear fuel to pools of water. However, since pools have been reaching their capacities, begin disposing of it beginning in 1998, owners and generators of spent nuclear fuel (typically utilities and reactor with plans for disposal in a national operators) have been transferring it to canisters that are placed in casks on repository. DOE, however, was unable concrete pads for dry storage—which is an expensive and time-consuming to meet the 1998 date and, as a result process. When operating reactors’ licenses begin to expire in the 2030s, the rate of lawsuits, the federal government has of spent nuclear fuel accumulation is expected to decrease, but the amount in dry paid out about $3.7 billion for storage storage will increase as the pools are closed and all spent nuclear fuel is costs.
    [Show full text]
  • Fuel Cycle Flexibility in CANDU P.G
    IAEA-SM-353-5P Fuel Cycle Flexibility in CANDU P.G. Boczar XA9949933 Director, Fuel and Fuel Cycle Division, AECL Chalk River Laboratories, Chalk River, Ontario, Canada No single fuel-cycle path is appropriate for all countries. Many local and global factors will affect the best strategy for an individual country. Fuel-cycle flexibility is an important factor in an ever-changing, and unpredictable world. CANDU is an evolutionary reactor, offering a custom fuel cycle to fit local requirements. Its unsurpassed fuel-cycle flexibility can accommodate the widest range of fuel-cycle options in existing CANDU stations. In the short term, the CANFLEX® bundle is nearing power reactor implementation. The demonstration irradiation of 26 bundles in the Pt. Lepreau power station in New Brunswick, Canada, started this September, and a water-CHF test will take place later this year that will confirm the improvement in thermalhydraulic performance. CANFLEX provides enhanced operating and safety performance through a reduction in peak linear element ratings, and a significant increase in critical channel power. CANFLEX will be the near-term carrier of advanced fuel cycles. While natural uranium fuel provides outstanding advantages, the use of slightly enriched uranium (SEU) in CANDU offers even lower fuel cycle costs and other potential benefits, such as uprating capability through flattening the radial channel power distribution. Recycled uranium (RU) from reprocessing spent PWR fuel is a subset of SEU that has significant economic promise. The use of SEU/RU is the first logical step from natural uranium in CANDU. For countries having LWR reactors, the ability to use low-fissile material in CANDU reactors offers a range of unique synergistic fuel cycle opportunities.
    [Show full text]
  • Spent Nuclear Fuel at the Indian Point Nuclear Power Station
    Spent Nuclear Fuel at the Indian Point Nuclear Power Station Robert Alvarez Institute for Policy Studies October 10, 2019 Why we should be concerned about spent power reactor fuel. The U.S. Government Accountability Office informed the U.S. Congress in April 2017 that “spent nuclear fuel can pose serious risks to humans and the environment ..and is a source of billions of dollars of financial liabilities for the U.S. government. According to the National Research Council and others, if not handled and stored properly, this material can spread contamination and cause long-term health concerns in humans or even death. ” Because of these extraordinary hazards spent nuclear fuel is required under federal law ( the Nuclear Waste Policy Act) to be disposed in a geological repository to prevent it from escaping into the human environment for tens-of-thousands of years. For these reasons, GAO concludes that spent power reactor fuel is “considered one of the most hazardous substances on Earth….” Sources: GAO- http://www.yuccamountain.org/pdf/gao-0517-684327.pdf, http://www.gao.gov/assets/660/653731.pdf When it closes by 2021, the Indian Point Nuclear Station in Buchanan, New York is estimated to have generated about 4,242 spent nuclear fuel assemblies (~1,951mt) containing approximately 865,368 spent fuel rods. The rods contain about 208 million ceramic uranium fuel pellets. After bombardment with neutrons in the reactor core, about 5 to 6 percent of the fuel is converted to a myriad of radioactive elements, with half-lives ranging from seconds to millions of years.
    [Show full text]
  • STORING SPENT FUEL UNTIL TRANSPORT to REPROCESSING OR DISPOSAL the Following States Are Members of the International Atomic Energy Agency
    IAEA Nuclear Energy Series No. NF-T-3.3 Basic Storing Spent Fuel Principles until Transport to Reprocessing or Objectives Disposal Guides Technical Reports INTERNATIONAL ATOMIC ENERGY AGENCY VIENNA ISBN 978–92–0–100719–3 ISSN 1995–7807 @ IAEA NUCLEAR ENERGY SERIES PUBLICATIONS STRUCTURE OF THE IAEA NUCLEAR ENERGY SERIES Under the terms of Articles III.A and VIII.C of its Statute, the IAEA is authorized to foster the exchange of scientific and technical information on the peaceful uses of atomic energy. The publications in the IAEA Nuclear Energy Series provide information in the areas of nuclear power, nuclear fuel cycle, radioactive waste management and decommissioning, and on general issues that are relevant to all of the above mentioned areas. The structure of the IAEA Nuclear Energy Series comprises three levels: 1 — Basic Principles and Objectives; 2 — Guides; and 3 — Technical Reports. The Nuclear Energy Basic Principles publication describes the rationale and vision for the peaceful uses of nuclear energy. Nuclear Energy Series Objectives publications explain the expectations to be met in various areas at different stages of implementation. Nuclear Energy Series Guides provide high level guidance on how to achieve the objectives related to the various topics and areas involving the peaceful uses of nuclear energy. Nuclear Energy Series Technical Reports provide additional, more detailed information on activities related to the various areas dealt with in the IAEA Nuclear Energy Series. The IAEA Nuclear Energy Series publications are coded as follows: NG — general; NP — nuclear power; NF — nuclear fuel; NW — radioactive waste management and decommissioning. In addition, the publications are available in English on the IAEA Internet site: http://www.iaea.org/Publications/index.html For further information, please contact the IAEA at PO Box 100, Vienna International Centre, 1400 Vienna, Austria.
    [Show full text]
  • NPR81: South Korea's Shifting and Controversial Interest in Spent Fuel
    JUNGMIN KANG & H.A. FEIVESON Viewpoint South Korea’s Shifting and Controversial Interest in Spent Fuel Reprocessing JUNGMIN KANG & H.A. FEIVESON1 Dr. Jungmin Kang was a Visiting Research Fellow at the Center for Energy and Environmental Studies (CEES), Princeton University in 1999-2000. He is the author of forthcoming articles in Science & Global Security and Journal of Nuclear Science and Technology. Dr. H.A. Feiveson is a Senior Research Scientist at CEES and a Co- director of Princeton’s research Program on Nuclear Policy Alternatives. He is the Editor of Science and Global Security, editor and co-author of The Nuclear Turning Point: A Blueprint for Deep Cuts and De-alerting of Nuclear Weapons (Brookings Institution, 1999), and co-author of Ending the Threat of Nuclear Attack (Stanford University Center for International Security and Arms Control, 1997). rom the beginning of its nuclear power program could reduce dependence on imported uranium. During in the 1970s, the Republic of Korea (South Ko- the 1990s, the South Korean government remained con- Frea) has been intermittently interested in the cerned about energy security but also began to see re- reprocessing of nuclear-power spent fuel. Such repro- processing as a way to address South Korea’s spent fuel cessing would typically separate the spent fuel into three disposal problem. Throughout this entire period, the constituent components: the unfissioned uranium re- United States consistently and effectively opposed all maining in the spent fuel, the plutonium produced dur- reprocessing initiatives on nonproliferation grounds. We ing reactor operation, and the highly radioactive fission review South Korea’s evolving interest in spent fuel re- products and transuranics other than plutonium.
    [Show full text]
  • THE NEXT GENERATION CANDU 6 J.M. HOPWOOD XA0053559 Atomic Energy of Canada Ltd, Mississauga, Ontario, Canada
    IAEA-SM-353/29 THE NEXT GENERATION CANDU 6 illinium J.M. HOPWOOD XA0053559 Atomic Energy of Canada Ltd, Mississauga, Ontario, Canada Abstract AECL's product line of CANDU 6 and CANDU 9 nuclear power plants are adapted to respond to chang- ing market conditions, experience feedback and technological development by a continuous improvement process of design evolution. The CANDU 6 Nuclear Power Plant design is a successful family of nuclear units, with the first four units entering service in 1983, and the most recent entering service this year. A further four CANDU 6 units are under construction. Starting in 1996, a focused forward-looking development program is under way at AECL to incorporate a series of individual improvements and integrate them into the CANDU 6, leading to the evolutionary development of the next-generation enhanced CANDU 6. The CANDU 6 improvements program includes all aspects of an NPP project, including engineering tools improvements, design for improved constructability, scheduling for faster, more streamlined commissioning, and improved operating performance. This enhanced CANDU 6 product will combine the benefits of design provenness (drawing on the more than 70 reactor-years experience of the seven operating CANDU 6 units), with the advantages of an evolutionary next- generation design. Features of the enhanced CANDU 6 design include: • Advanced Human Machine Interface - built around the Advanced CANDU Control Centre. • Advanced fuel design - using the newly demonstrated CANFLEX fuel bundle. • Improved Efficiency based on improved utilization of waste heat. • Streamlined System Design - including simplifications to improve performance and safety system reliability. • Advanced Engineering Tools, - featuring linked electronic databases from 3D CADDS, equipment specifi- cation and material management.
    [Show full text]
  • Backgrounder: Dry Cask Storage of Spent Nuclear Fuel
    h Dry Cask Storage of Spent Nuclear Fuel Nuclear plants were originally designed to provide temporary onsite storage of used nuclear fuel. Known as “spent fuel,” these bundles of fuel rods must be replaced from time-to-time because they lose efficiency. About one-third of the nuclear fuel in a reactor is removed and replaced with fresh fuel at each refueling. The spent fuel, which generates considerable heat and radiation, is placed into deep pools of water at the reactor site, where it can be stored safely. Reactor designers expected spent fuel to be stored in pools for a few years before it was shipped offsite to be “reprocessed.” A reprocessing plant would separate portions that could be recycled into new fuel; unusable portions would be disposed as waste. But commercial reprocessing never succeeded in the United States, so pools began to fill up. Pools Reach Capacity As spent fuel accumulated in the pools in the early 1980s, utilities began to look at options for increasing the amount they could store. The pools are robust structures that cannot be enlarged. So utilities needed to fit more fuel into their pools. Current regulations permit two options for expanding pool capacity: re-racking (replacing storage racks to decrease the distance between assemblies) and fuel rod consolidation (removing fuel rods from the assemblies to pack them more densely for storage). The NRC must review and approve any such changes. But pool capacity can only be expanded so far. Enter Dry Storage Utilities began turning to dry storage to manage their spent fuel onsite.
    [Show full text]
  • Pacific Basin Nuclear Conference (PBNC 2018)
    Pacific Basin Nuclear Conference (PBNC 2018) Advancing and Sustaining Nuclear Energy San Francisco, California, USA 30 September - 4 October 2018 Volume 1 of 2 ISBN: 978-1-5108-7472-5 Printed from e-media with permission by: Curran Associates, Inc. 57 Morehouse Lane Red Hook, NY 12571 Some format issues inherent in the e-media version may also appear in this print version. Copyright© (2018) by American Nuclear Society All rights reserved. Printed by Curran Associates, Inc. (2019) For permission requests, please contact American Nuclear Society at the address below. American Nuclear Society 555 North Kensington Avenue La Grange Park, Illinois 60526 USA Phone: (800) 323-3044 (708) 352-6611 Fax: (708) 352-0499 www.ans.org Additional copies of this publication are available from: Curran Associates, Inc. 57 Morehouse Lane Red Hook, NY 12571 USA Phone: 845-758-0400 Fax: 845-758-2633 Email: [email protected] Web: www.proceedings.com TABLE OF CONTENTS VOLUME 1 PROBABILITY RISK ASSESSMENT, SAFETY, AND CONTROL SYSTEMS Site-Specific PSR Process for Kori-1 Permanent Shut-Down NPP ..............................................................................................................1 Dong Wook Kim PSA-Based Design Extension of Existing PWR Plant and Application in the Design of Advanced PWR Plant.....................................6 Wenkui Lu, Jing Liu, Jinlong Sun, Chao Ma, Xinli Yu Evaluation on the PSA Digital and Analog Instrumentation and Control System in Advanced Nuclear Power Plant .......................12 Zhuo Chen, Jian Yang, Wei Deng Control System Software Common Cause Failure Analysis for APR1400................................................................................................22 Jong-Cheol Park, Min Shin Jung, Jong Ho Choi, Gyu Cheon Lee REACTOR SAFETY ANALYSIS METHODOLOGIES AND CODES - I Comparative Analysis of Different Configurations to Enhance the ESBWR Passive Cooling Systems.................................................26 J.
    [Show full text]
  • Radiation Safety Information Computational Center
    Radiation Safety Information Computational Center Oak Ridge National Laboratory POST OFFICE BOX 2008 OAK RIDGE, TENNESSEE 37831-6362 Managed by UT-Battelle, LLC for the U.S. Department of Energy under contract DE-AC05-00OR22725 Phone No. 865-574-6176 FAX 865-574-6182 Internet: [email protected] http://www-rsicc.ornl.gov/rsic.html No. 448 June 2002 "The measure of a man's real character is what he would do if he knew he never would be found out." -- Thomas B. Macaulay Printable PDF file of this newsletter available at: http://www-rsicc.ornl.gov/NEWSLETTER.html. Azmy Elected as Fellow to ANS Congratulations to Dr. Yousry Azmy, ORNL, for being elected to Fellow Membership of the American Nuclear Society. The ANS is recognizing Dr. Azmy's contributions to the advancement of nuclear science and technology through the years. Dr. Azmy is a member of the Radiation Protection and Shielding Division and Mathematics and Computation Division. He will be honored at the Awards Luncheon June 11, in Hollywood, Florida. NOTICE RSICC will be offering a few data, processing, and computational tools free of handling, testing, and other fees associated with package transmittal. A ***NO FEE*** label will appear next to the package name on the web request page. The ability to provide these packages at no charge is due in part to advanced funding from the sponsors. To acquire these tools, follow the normal registration procedure for first-time or updated users. Then complete the WWW Request Form. The license and export control statements will need the user signatures, which is standard procedure.
    [Show full text]
  • Lightning Effects on Holtec on Dry Cask Storage Systems
    ORNL/TM-2002/192 ORNL/NRC/LTR-02/08 Program Title: Lightning Effects on Dry Cask Storage Systems Document Title: Analysis of Lightning Strike Effects on a Holtec Hi-Storm 100 Dry Cask Storage System for Spent Nuclear Fuel Document Type: Letter Report, rev. 1 Author: J.J. Yugo NRC Manager: C.E. Antonescu ORNL Manager: R.T. Wood Prepared for U.S. Nuclear Regulatory Commission under DOE Interagency Agreement 1886-N662-4Y NRC JCN No. Y6624 Prepared by the Nuclear Science and Technology Division OAK RIDGE NATIONAL LABORATORY P.O. Box 2008 Oak Ridge, Tennessee 37831-6285 managed by UT-Battelle, LLC for the U.S. DEPARTMENT OF ENERGY under contract DE-AC05-00OR22725 Notice 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, or any of their employees, makes any warranty, expressed or implied, or assumes any legal liability or responsibility for any third party's use, or the results of such use, of any information, apparatus, product or process disclosed in this report, or represents that its use by such third party would not infringe privately owned rights. 0 TABLE OF CONTENTS TA BLE O F CO N TENTS ............................................................................................................................ iii LIST O F FIGU RES ...................................................................................................................................... v A BSTRA CT ...............................................................................................................................................
    [Show full text]
  • Interim Storage of Spent Nuclear Fuel: a Safe, Flexible, and Cost-Effective Approach to Spent Fuel Management
    Interim Storage of Spent Nuclear Fuel: A Safe, Flexible, and Cost-Effective Approach to Spent Fuel Management The Harvard community has made this article openly available. Please share how this access benefits you. Your story matters Citation Bunn, Matthew, John P. Holdren, Allison Macfarlane, Susan E. Pickett, Atsuyuki Suzuki, Tatsujiro Suzuki, and Jennifer Weeks. 2001. Interim Storage of Spent Nuclear Fuel: A Safe, Flexible, and Cost-Effective Approach to Spent Fuel Management. Cambridge: Managing the Atom Project, Harvard University and Project on Sociotechnics of Nuclear Energy, University of Tokyo Published Version http://belfercenter.ksg.harvard.edu/publication/2150/ interim_storage_of_spent_nuclear_fuel.html Citable link http://nrs.harvard.edu/urn-3:HUL.InstRepos:29914175 Terms of Use This article was downloaded from Harvard University’s DASH repository, and is made available under the terms and conditions applicable to Other Posted Material, as set forth at http:// nrs.harvard.edu/urn-3:HUL.InstRepos:dash.current.terms-of- use#LAA Interim Storage of Spent Nuclear Fuel A Safe, Flexible, and Cost-Effective Near-Term Approach to Spent Fuel Management A Joint Report from the Harvard University Project on Managing the Atom and the University of Tokyo Project on Sociotechnics of Nuclear Energy Matthew Bunn Harvard University University of Tokyo John P. Holdren Allison Macfarlane Susan E. Pickett Atsuyuki Suzuki Project on Managing Tatsujiro Suzuki Project on Sociotechnics the Atom of Nuclear Energy Jennifer Weeks June, 2001 Interim Storage of Spent Nuclear Fuel A Safe, Flexible, and Cost-Effective Near-Term Approach to Spent Fuel Management Matthew Bunn John P. Holdren Allison Macfarlane Susan E.
    [Show full text]