DOCSLIB.ORG

NUREG-1571: Information Handbook on Independent Spent Fuel Storage

Total Page：16

File Type：pdf, Size：1020Kb

Download full-text PDF Read full-text
NUREG-1571: Information Handbook on Independent Spent Fuel Storage NUREG- 1571 Information Handbook on Independent Spent Fuel Storage Installations U.S. Nuclear Regulatory Commission Office of Nuclear Material Safety and Safeguards M. G. Raddatz, M. D. Waters i AVAILABILITY NOTICE Availability of Reference Materials Cited in NRC Publications Most documents cited in NRC publications will be available from one of the following sources: 1. The NRC Public Document Room, 2120 L Street, NW., Lower Level, Washington, DC 20555-0001 2. The Superintendent of Documents, U.S. Government Printing Office, P. 0. Box 37082, Washington, DC 20402-9328 3. The National Technical Information Service, Springfield, VA 22161-0002 Although the listing that follows represents the majority of documents cited in NRC publica tions, it is not intended to be exhaustive. Referenced documents available for inspection and copying for a fee from the NRC Public Document Room include NRC correspondence and internal NRC memoranda; NRC bulletins, circulars, information notices, inspection and investigation notices; licensee event reports; vendor reports and correspondence; Commission papers; and applicant and licensee docu ments and correspondence. The following documents in the NUREG series are available for purchase from the Government Printing Office: formal NRC staff and contractor reports, NRC-sponsored conference pro ceedings, international agreement reports, grantee reports, and NRC booklets and bro chures. Also available are regulatory guides, NRC regulations in the Code of Federal Regula tions, and Nuclear Regulatory Commission Issuances. Documents available from the National Technical Information Service include NUREG-series reports and technical reports prepared by other Federal agencies and reports prepared by the Atomic Energy Commission, forerunner agency to the Nuclear Regulatory Commission. Documents available from public and special technical libraries include all open literature items, such as books, journal articles, and transactions. Federal Register notices, Federal and State legislation, and congressional reports can usually be obtained from these libraries. Documents such as theses, dissertations, foreign reports and translations, and non-NRC con ference proceedings are available for purchase from the organization sponsoring the publica tion cited. Single copies of NRC draft reports are available free, to the extent of supply, upon written request to the Office of Administration, Distribution and Mail Services Section, U.S. Nuclear Regulatory Commission, Washington DC 20555-0001. Copies of industry codes and standards used in a substantive manner in the NRC regulatory process are maintained at the NRC Library, Two White Flint North, 11545 Rockville Pike, Rock ville, MD 20852-2738, for use by the public. Codes and standards are usually copyrighted and may be purchased from the originating organization or, if they are American National Standards, from the American National Standards Institute, 1430 Broadway, New York, NY 10018-3308. NUREG- 1571 Information Handbook on Independent Spent Fuel Storage Installations Manuscript Completed: December 1996 Date Published: December 1995 M. G. Raddatz, M. D. Waters Spent Fuel Project Office Office of Nuclear Material Safety and Safeguards U.S. Nuclear Regulatory Commission Washington, DC 20555-0001 ABSTRACT ABSTRACT In this information handbook, the staff of the U.S. Nuclear Regulatory Commission describes (1) background information regarding the licensing and history of independent spent fuel storage installations (ISFSIs), (2) a discussion of the licensing process, (3) a description of all currently approved or certified models of dry cask storage systems (DCSSs), and (4) a description of sites currently storing spent fuel in an ISFSI. Storage of spent fuel at ISFSIs must be in accordance with the provisions of 10 CFR Part 72. The staff has provided this handbook for information purposes only. The accuracy of any information herein is not guaranteed. For verification or for more details, the reader should refer to the respective docket files for each DCSS and ISFSI site. The information in this handbook is current as of September 1, 1996. Comments, which would make future revisions of this handbook more useful, are invited and should be directed to: Mr. Michael D. Waters Spent Fuel Project Office Office of Nuclear Material Safety and Safeguards U.S. Nuclear Regulatory Commission Washington, D.C. 20555-0001 iii NUREG-1571 CONTENTS CONTENTS Page A B ST RA CT ................................................................ iii ACRONYMS AND ABBREVIATIONS ........................................... ix ACKNOW LEDGM ENTS ....................................................... xi 1 INTRO D UCTIO N ........................................................ 1-1 1.1 B ackground ......................................................... 1-1 1.2 Licensing H istory ..................................................... 1-1 1.3 Overview of Current ISFSIs (September 1996) ............................... 1-5 1.4 R eferences .......................................................... 1-5 2 LICENSING PROCESSES .................................................. 2-1 2.1 Site-Specific License .................................................. 2-1 2.2 G eneral License ...................................................... 2-3 2.3 License Advantages and Disadvantages .................................... 2-4 2.4 Applicable Regulatory Guides and Additional Guidance ........................ 2-5 3 APPROVED DRY CASK STORAGE SYSTEMS ................................ 3-1 3.1 Castor V/2 1: Certificate of Compliance #1000 ............................... 3-3 3.2 C astor X/33 ......................................................... 3-9 3.3 MC-10: Certificate of Compliance #1001 .................................. 3-12 3.4 Modular Vault Dry Store (MVDS) System ................................. 3-16 3.5 NAC-S/T: Certificate of Compliance #1002 ................................ 3-21 3.6 N AC-I28 S/T ....................................................... 3-24 3.7 NAC-C28 S/T: Certificate of Compliance #1003 ............................ 3-26 3.8 N A C -STC ......................................................... 3-27 3.9 N U H O M S-7P ...................................................... 3-29 3.10 NUH OM S-24P ..................................................... 3-35 3.11 Standardized NUHOMS-24P/52B: Certificate of Compliance #1004 ............. 3-42 3.12 TN -40 ............................................................ 3-4 7 3.13 TN-24: Certificate of Compliance #1005 .................................. 3-51 3.14 VSC-24: Certificate of Compliance #1007 ................................. 3-55 4 SITE-SPECIFIC ISFSIs ..................................................... 4-1 4.1 Calvert Cliffs ISFSI (Docket 72-8) ........................................ 4-2 4.2 Fort St. Vrain ISFSI (Docket 72-9) ........................................ 4-7 4.3 H. B. Robinson ISFSI (Docket 72-3) ...................................... 4-12 4.4 Oconee ISFSI (Docket 72-4) ............................................ 4-16 4.5 Prairie Island ISFSI (Docket 72-10) ...................................... 4-19 4.6 Surry ISFSI (Docket 72-2) ............................................. 4-25 ¥ NUREG-1571 CONTENTS Page 5 GENERAL LICENSE ISFSIs ................................................ 5-1 5.1 Arkansas Nuclear One ISFSI (Docket 72-13) ................................ 5-2 5.2 Davis-Besse ISFSI (Docket 72-14) ........................................ 5-3 5.3 Palisades ISFSI (Docket 72-7) ........................................... 5-4 5.4 Point Beach ISFSI (Docket 72-5) ......................................... 5-8 6 CURRENT LICENSE APPLICATIONS ........................................ 6-1 7 MRS/MPC AND PRIVATE AWAY-FROM-REACTOR INITIATIVES (for later use) .... 7-1 FIGURES 1.3-1 Current U.S. ISFSIs .............. .. .. .. .. 1-6 1.3-2 Potential ISFSIs Needed in Near Future ........... ... .. ... ..... ... .. ......... 1-7 1.3-3 Time-Line of DCSS and ISFSI Licen sing/Operating Dates . ........ 1-8 2.1-1 Site-Specific Licensing Process .... ........ 2-7 2.2-1 General Licensing Process ......................... ........ 2-8 2.2-2 Certificate of Compliance Issuing Process .............. ........ 2-9 3.1-1 Diagram of the Castor V/21 ........................ ........ 3-5 3.1-2 Photograph of the Castor V/21 ...................... ........ 3-6 3.1-3 Photograph of Fuel Basket Inside the MC-10 ........... ........ 3-7 3.1-4 Photograph of Castor V/21 in the Surry Power Station SFP. ........ 3-8 3.2-1 Diagram of the Castor X/33 ........................ ....... 3-11 3.3-1 Diagram of the M C- 10 ............................ ....... 3-14 3.3-2 Photograph of the M C- 10 .......................... ....... 3-15 3.4-1 Diagram of the MVDS System ...................... ....... 3-18 3.4-2 Photograph of the MVDS System .................... ....... 3-19 3.4-3 Photograph of a MVDS FSC ....................... ....... 3-20 3.5-1 Diagram of the NAC-S/T General Cask Design ......... ....... 3-23 3.9-1 Diagram of the NUHOMS-7P DSC .................. ....... 3-31 3.9-2 Diagram of the NUHOMS-7P HSM .................. ....... 3-32 3.9-3 Photograph of an HMS array ....................... ....... 3-33 3.9-4 NUHOMS-7P Fuel Handling Procedures .............. ....... 3-34 3.10-1 Diagram of the NUHOMS-24P DSC ................. ....... 3-38 3.10-2 Diagram of the NUHOMS-24P HSM ................. ....... 3-39 3.10-3 Diagram of a NUHOMS On-Site Transfer Cask ......... ......
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]
  • 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]
  • 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]
  • 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]
  • Advantages of Dry Hardened Cask Storage Over Wet Storage for Spent Nuclear Fuel
    2011 International Nuclear Atlantic Conference - INAC 2011 Belo Horizonte,MG, Brazil, October 24-28, 2011 ASSOCIAÇÃO BRASILEIRA DE ENERGIA NUCLEAR - ABEN ISBN: 978-85-99141-04-5 ADVANTAGES OF DRY HARDENED CASK STORAGE OVER WET STORAGE FOR SPENT NUCLEAR FUEL Luiz Sergio Romanato Departamento da Qualidade Centro Tecnológico da Marinha em São Paulo Av. Professor Lineu Prestes 2468 05508-000 São Paulo, SP [email protected] ABSTRACT Pools are generally used to store and maintain spent nuclear fuel assemblies for cooling, after removed from reactors. After three to five years stored in the pools, spent fuel can be reprocessed or sent to a final disposition in a geological repository and handled as radioactive waste or sent to another site waiting for future solution. Spent fuel can be stored in dry or wet installations, depending on the method adopted by the nuclear plant. If this storage were exclusively wet, at the installation decommissioning in the future, another solution for storage will need to be found. Today, after a preliminary cooling, the spent fuel assemblies can be removed from the pool and sent to dry hardened storage installations. This kind of storage does not need complex radiation monitoring and it is safer than wet storage. Brazil has two nuclear reactors in operation, a third reactor is under construction and they use wet spent fuel storage . Dry hardened casks use metal or both metal and concrete for radiation shielding and they are safe, especially during an earthquake. An earthquake struck Japan on March 11, 2011 damaging Fukushima Daiichi nuclear power plant.
    [Show full text]
  • Methods to Enhance Spent Fuel Pool and Dry Cask Storage
    University of Tennessee, Knoxville TRACE: Tennessee Research and Creative Exchange Supervised Undergraduate Student Research Chancellor’s Honors Program Projects and Creative Work 5-2014 Methods to Enhance Spent Fuel Pool and Dry Cask Storage Dustin Giltnane University of Tennessee - Knoxville, [email protected] David Gotthold University of Tennessee - Knoxville, [email protected] Seth Langford University of Tennessee - Knoxville, [email protected] Michael Ratliff University of Tennessee - Knoxville, [email protected] Jessica Dawn Shewmaker University of Tennessee - Knoxville, [email protected] See next page for additional authors Follow this and additional works at: https://trace.tennessee.edu/utk_chanhonoproj Part of the Nuclear Engineering Commons Recommended Citation Giltnane, Dustin; Gotthold, David; Langford, Seth; Ratliff, Michael; Shewmaker, Jessica Dawn; and Wiggins, Cody, "Methods to Enhance Spent Fuel Pool and Dry Cask Storage" (2014). Chancellor’s Honors Program Projects. https://trace.tennessee.edu/utk_chanhonoproj/1786 This Dissertation/Thesis is brought to you for free and open access by the Supervised Undergraduate Student Research and Creative Work at TRACE: Tennessee Research and Creative Exchange. It has been accepted for inclusion in Chancellor’s Honors Program Projects by an authorized administrator of TRACE: Tennessee Research and Creative Exchange. For more information, please contact [email protected]. Author Dustin Giltnane, David Gotthold, Seth Langford, Michael Ratliff, Jessica Dawn Shewmaker, and Cody Wiggins This dissertation/thesis is available at TRACE: Tennessee Research and Creative Exchange: https://trace.tennessee.edu/utk_chanhonoproj/1786 Methods to Enhance Spent Fuel Pool and Dry Cask Storage Dustin Giltnane Dave Gotthold Seth Langford Michael Ratliff Jessica Shewmaker Cody Wiggins Professor: M.
    [Show full text]
  • Waste Control Specialists, LLC, Consolidated Interim Spent Fuel
    WASTE CONTROL SPECIALISTS LLC ATTACHMENT 1-1 ENVIRONMENTAL REPORT ATTACHMENT 1-1 LETTERS Page A1-1-1 Revision 0 IN THE COMMISSIONERS COURT OF ANDREWS COUNTY, TEXAS A resolution in support ofestablishing a site in Andrews County for consolidated interim storage ofspent nuclear fuel and high-level radioactive waste. WHEREAS, Andrews County, Texas, as host to two low-level radioactive waste disposal facilities operated by Waste Control Specialists LLC ("WCS"), greatly benefits directly and indirectly from the economic activity associated with disposal of radioactive materials; and WHEREAS, Andrews County recognizes the importance of a diversified economy to the livelihood of the citizens of Andrews County; and WHEREAS, Andrews County is home to a specialized workforce with expertise concerning radioactive materials, and WCS currently employs more than 170 full-time employees with an annual payroll of more than $13 million in Andrews County; and WHEREAS, Andrews County has invested in the success of the low-level radioactive waste disposal facilities operated by WCS by issuing $75 million in bonds and using that revenue to purchase property leased by WCS as part of the operation of the disposal facilities; and WHEREAS, Andrews County receives five percent of the gross receipts from waste disposed of at the two low-level radioactive waste disposal facilities, which receipts to date have totaled over $5 million directly paid to Andrews County and are expected to total more than $3 million per year in the future; and WHEREAS, WCS has consistently
    [Show full text]
  • Methodologies for Imaging a Used Nuclear Fuel Dry
    METHODOLOGIES FOR IMAGING A USED NUCLEAR FUEL DRY STORAGE CASK WITH COSMIC RAY MUON COMPUTED TOMOGRAPHY A Dissertation Presented for the Doctor of Philosophy Degree The University of Tennessee, Knoxville Zhengzhi Liu August 2018 ACKNOWLEDGEMENTS Life is a journey of ups and downs. This is also true of doing research. This dissertation would not have come into being without the kind help and support received from many people. My first and foremost appreciation goes to my mentor and academic advisor Prof. Jason P Hayward for guiding me through the tough times of my graduate study. As a Chinese proverb said “Give a man a fish and you feed him for a day. Teach a man to fish and you feed him for a lifetime.” Prof. Hayward’s incisive and heuristic intellectual guidance deeply inspired me to unearth the truth and find the resolution to the problems. His scientifically rigorous research attitude shaped my way to treat studies, experiments and research. His unwavering patience and accessible personality restored my confidence again and again at challenging times, just like a father who would never forsake his son. I am forever grateful for Prof. Haywards’ teaching, guidance, help and the innumerous amount of time he has spent with me. I would also like to sincerely thank my co-mentor Dr. Chatzidakis Stylianos for his selfless guidance and help. He encouraged me to think out of the box, looking at the problems from novel angles. I am deeply grateful for his encouragement and pushing me forward, which significantly fostered my intellectual growth. In life, he is one of my best friends.
    [Show full text]