Regulatory Guide 1.60
Regulatory Guide 1.60
<p>Regulatory Guide 1.60 DESIGN RESPONSE SPECTRA FOR SEISMIC DESIGN OF NUCLEAR POWER PLANTS</p>
<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.
This CSNF handling study evaluates the handling of CSNF in air and packaging activities. It evaluates a facility design, further identifies the fuel performance issues, develops the consequences, and presents the operational considerations associated with the routine handling of CSNF in air. Emphasis is on the process of oxidation of
uranium dioxide fuel and additional oxidation-driven failure of fuel assembly cladding. Key
issues are identified, and plans to address these issues are proposed.
Per the requirements of the Task Order 21: Operational Requirements for Standardized Dry Fuel Canister Systems, Statement of Work (SOW), EnergySolutions and its team partners: NAC International, Booz Allen Hamilton and Exelon Nuclear Partners, hereafter referred to as “the Team”, is providing for the U.S. Department of Energy (DOE) an Updated Final Report, which documents the results from the studies performed.
Under Task Order 17 of the industry Advisory and Assistance Contract to the Department of
Energy (DOE) DE-NE0000291, the AREVA Team has provided a conceptual design for a
reusable transportation cask (the 6625B-HB) capable of transporting BWR and PWR used
nuclear fuel (UNF) assemblies, including high burnup UNF. These assemblies can be shipped
either as bare fuel or fuel loaded into damaged fuel canisters (DFCs). The 6625B-HB cask has
been designed with reasonable assurance it can be licensed by the Nuclear Regulatory
This report documents the concepts, feasibility, advantages, disadvantages and recommendations for STAD canister systems developed by EnergySolutions and its team of partners: NAC International, Talisman International, Booz Allen Hamilton, TerranearPMC, Exelon Nuclear Partners and Sargent & Lundy, hereafter referred to as “the Team”.
Per the requirements of the Task Order 17: Spent Nuclear Fuel Transportation Cask Design
Study, statement of work (SOW), EnergySolutions and its team partners: NAC International,
Talisman International, Booz Allen Hamilton and Exelon Nuclear Partners, hereafter referred to
as “the Team”, is providing a final report for U.S. Department of Energy (DOE) review, which
documents the cask concepts developed under this study and the results of supporting analysis
work.
This report provides information on the inventory of commercial spent nuclear fuel, referred to herein as used nuclear fuel (UNF), as well as Government-owned UNF and high-level radioactive waste (HLW). Actual or estimated quantitative values for current inventories are provided along with inventory forecasts derived from examining a different future commercial nuclear power generation scenarios. The report also includes select information on the characteristics associated with the wastes examined (e.g. type, packaging, heat generation rate, decay curves).