Process Flow Diagrams and Node Descriptions (PFDND) for the WMS
Process Flow Diagrams and Node Descriptions (PFDND) for the WMS
Slides - Institiute of Nuclear Materials Management Annual Meeting (INMM), Atlanta GA, July 20-24, 2014
Slides - Institiute of Nuclear Materials Management Annual Meeting (INMM), Atlanta GA, July 20-24, 2014
Slides - Institute of Nuclear Materials Management Annual Meeting, Atlanta GA, July 20-24, 2014
Slides - Institute of Nuclear Materials Management Annual Meeting (INMM), July 20-24 2014, Atlanta GA
Slides - Institute of Nuclear Materials Management, 55th Annual Meeting, July 20 – 24, 2014 Atlanta, Georgia
This document is a compilation of publically-available information on spent/used nuclear fuel storage and transport casks in use in the United States as of the summer of 2013. As such, it is a functional update and extension of JAI-582, “Shipping and Storage Cask Data For Commercial Spent Nuclear Fuel,” originally published by JAI Corporation in March 2005[1]. This report is intended to provide a convenient reference for those with interest in, or those engaged in the production, handling, storage, transport, and disposition of spent/used commercial nuclear fuel.
The Yucca Mountain repository is designed to provide a permanent solution for managing nuclear waste, minimize the uncertainty of future waste safety, and enable DOE to begin fulfilling its legal obligation under the Nuclear Waste Policy Act to take custody of commercial waste, which began in 1998. However, project delays have led to utility lawsuits that DOE estimates are costing taxpayers about $12.3 billion in damages through 2020 and could cost $500 million per year after 2020, though the outcome of pending litigation may affect the government’s total liability.
<p>Regulatory Guide 1.60 DESIGN RESPONSE SPECTRA FOR SEISMIC DESIGN OF NUCLEAR POWER PLANTS</p>
This publication is a compilation of international experience with cask contamination problems
and decontamination practices. The objective is to represent current knowledge and experience as well
as developments, trends and potential for new applications in this field. Furthermore, the report may
assist in new design or modification of existing casks, cask handling systems and decontamination
equipment. The annexes contain figures of several cask types for illustration.
Presentation made at International Conference on The Management of Spent Nuclear Fuel from Nuclear Power Reactors, An Integrated approach to the Back-End of the Fuel Cycle (IAEA-CN-226). The purpose of the conference was to highlight the importance of an integrated long-term approach to the management of spent fuel from nuclear power reactors.
This presentation was given at the Nuclear Waste Technical Review Board (NWTRB) meeting June 24, 2015 in Golden, Colorado. It covered the standardized transportation, aging, and disposal (STAD) canister design work being performed by DOE and responded to a number of NWTRB questions.
These slides were presented by Waste Control Specialists LLC (WCS) to the NRC at the June 16, 2015 pre-application public meeting at the NRC offices in Rockville, Maryland.
Presentation made at International Conference on The Management of Spent Nuclear Fuel from Nuclear Power Reactors, An Integrated approach to the Back-End of the Fuel Cycle (IAEA-CN-226). The purpose of the conference was to highlight the importance of an integrated long-term approach to the management of spent fuel from nuclear power reactors.
Presentation made at International Conference on The Management of Spent Nuclear Fuel from Nuclear Power Reactors, An Integrated approach to the Back-End of the Fuel Cycle (IAEA-CN-226). The purpose of the conference was to highlight the importance of an integrated long-term approach to the management of spent fuel from nuclear power reactors.
Presentation made at International Conference on The Management of Spent Nuclear Fuel from Nuclear Power Reactors, An Integrated approach to the Back-End of the Fuel Cycle (IAEA-CN-226). The purpose of the conference was to highlight the importance of an integrated long-term approach to the management of spent fuel from nuclear power reactors.
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<p><span style="font-size: 12.000000pt; font-family: 'TimesNewRomanPSMT'">This report fulfills the M1 milestone M11UF041401, “Storage R&D Opportunities Report” under Work Package Number FTPN11UF0414. </span></p>
<p>This presentation was given at Oak Ridge National Laboratory on May 20, 2014. It describes the Centralized Used Fuel Resource for Information Exchange (CURIE) and how to register, log-in, and upload documents among other capabilities. </p>
Slides - 2014 National Tranpsortation Stakeholders Forum, Bloomington, MN, May 13-15, 2104
Understanding the changing nuclear and mechanical characteristics of used nuclear fuel (UNF) over time and how these changing characteristics affect storage, transportation, and disposal options can require many tools and types of data. To streamline analysis capabilities for the waste management system, a comprehensive, integrated data and analysis tool has been assembled—UNF-Storage, Transportation & Disposal Analysis Resource and Data System (UNF-ST&DARDS).
Presentation by Ron Pope and Yung Liu of Argonne National Laboratory to the World Institute for Nuclear Security (WINS) Workshop on Security of Dry Storage of Spent Nuclear Fuel
Slides - World Institute for Nuclear Security (WINS), Security of Dry Storage of Spent Nuclear Fuel, Vilnius, Lithuania, June 10-12, 2014
Slides - National Tranpsortation Stakeholders Forum, Minneapolis, MN, May, 14, 2014
Performance Specification: This performance specification document addresses use of a standardized transportation, aging, and
disposal (STAD) canister system in the spent nuclear fuel (SNF) waste management system. This
document was developed to support STAD canister system studies and potential research, development,
and demonstration activities. Requirements in this specification may evolve with time based on results
from analyses, experiments, design studies, system evaluations and demonstrations, as well as other
factors.
NFST Overview presentation given at the Nuclear Decommissioning & Used Fuel Strategy Summit, Charlotte SC, October 5, 2015.