UNF-STANDARDS presentation to EPRI extended storage collaboration project

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 made at IAEA on A Unified Spent Nuclear Fuel (SNF) Database and Analysis System

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.

Sister Rod Examinations at ORNL for the HBU Spent Fuel Data Project

Presentation made at the Electric Power Research Institute (EPRI) Extended Storage Collaboration Project (ESCP) meeting November 2016 discussing the status of nondestructive examinations being performed on high burnup (HBU) sent nuclear fuel (SNF) rods at Oak Ridge National Laboratory and proposed destructive examinations that will be performed over the next several years.

Potential Nuclear Power Plant Closings in Illinois - Impacts and Market-Based Solutions

HR1146 Report - Response to the Illinois General Assembly concerning House Resolution 1146.

Lessons Learned from the West Valley Spent Nuclear Fuel Shipment within the United States

This paper describes the lessons learned from the U.S. Department of Energy (DOE) transportation of 125 DOE-owned commercial spent nuclear fuel (SNF) assemblies by railroad from the West Valley Demonstration Project to the Idaho National Engineering and Environmental Laboratory (INEEL). On July 17, 2003, DOE made the largest single shipment of commercial SNF in the history of the United States. This was a highly visible and political shipment that used two specially designed Type B transportation and storage casks. This paper describes

PRELIMINARY ASSESSMENT OF COSTS AND RISKS OF TRANSPORTING SPENT FUEL BY BARGE

The purpose of this study is to analyze the costs and risks associated with transporting spent fuel by barge. The barge movements would be made in combination with rail movements to transport spent fuel from plants to a repository. For the purposes of this analysis, three candidate repository sites are analyzed: Yucca Mountain, Nevada, Deaf Smith, Texas, and Hanford, Washington. This report complements a report prepared by Sandia National Laboratories in 1984 that analyzes the costs and risks of transporting spent fuel by rail and by truck to nine candidate repository sites.

WCS Resolution

In the commissioners court of Andrews County, Texas A resolution in support of establishing a site in Andrews County for consolidated interim storage of spent nuclear fuel and high-level radioactive waste.

Considerations for Disposition of Dry Cask Storage System Materials at End of Storage System Life

Dry cask storage systems are deployed at nuclear power plants for used nuclear fuel (UNF)

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

The Used Nuclear Fuel-Storage, Transportation & Disposal Analysis Resource and Data System (UNF-ST&DARDS)

Slides - Institute of Nuclear Materials Management Annual Meeting, Atlanta GA, July 20-24, 2014

Feasibility of Direct Disposal of Dual-Purpose Canister From a Criticality Perspective

Slides - Institute of Nuclear Materials Management Annual Meeting (INMM), July 20-24 2014, Atlanta GA

Nuclear Fuel Data Survey, Form GC-859, Rev. May 2013

This is the May 2013 revision to Form GC-859, Nuclear Fuel Data Survey, downloaded from the EIA site on September 12, 2014. This form requires license holders to provide the data defined within the form for spent nuclear fuel as of June 30, 2013. This survey is similar to the older RW-859 surveys.

NFST Transportation Program Overview

Slides - 2014 National Tranpsortation Stakeholders Forum, Bloomington, MN, May 13-15, 2104

Further Calculations using the QSS and RTM Computer Models

With the QSS Model, calculations have been undertaken in NRVB (Nirex Repository Vault Backfill) where a system can encounter positive temperature feedback when the pore water boils. A QSS calculation of two or more stages is required when this occurs. The QSS Model has also been used to undertake calculations in mudstone, a potential GDF host rock that has not been studied previously.

DOE’s Centralized Storage Design Alternatives and Security Regulations

Slides - World Institute for Nuclear Security (WINS), Security of Dry Storage of Spent Nuclear Fuel, Vilnius, Lithuania, June 10-12, 2014

What to Expect When Readying to Move Spent Nuclear Fuel from Commercial Nuclear Power Plants

Slides - National Tranpsortation Stakeholders Forum, Minneapolis, MN, May, 14, 2014

EPRI Review of Geologic Disposal for Used Fuel and High Level Radioactive Waste: Volume IV—Lessons Learned

The effective termination of the Yucca Mountain program by the U.S. Administration in 2009 has further delayed the construction and operation of a permanent disposal facility for used fuel and high level radioactive waste (HLW) in the United States. In concert with this decision, the President directed the Energy Secretary to establish the Blue Ribbon Commission on America’s Nuclear Future to review and provide recommendations on options for managing used fuel and

An Economic Analysis of Select Fuel Cycles Using the Steady-State Analysis Model for Advanced Fuel Cycles Schemes (SMAFS)

This report evaluates the relative economics of alternative fuel cycles compared to the current U.S. once-through fuel cycle, including concepts under consideration by the U.S. Department of Energy’s (DOE) Global Nuclear Energy Partnership (GNEP). EPRI utilized a model developed by the Nuclear Energy Agency (NEA), Steady-state analysis Model for Advanced Fuel Cycle Schemes (SMAFS), to evaluate fuel cycle alternatives. The report also evaluates potential financing options for a fuel recycling facility. Please note that this report contains preliminary

Program on Technology Innovation: Advanced Fuel Cycles—Impact on High-Level Waste Disposal: Analysis of Deployment Scenarios of Fast Burner Reactors in the U.S. Nuclear Fleet

This report presents the results of a dynamic simulation analysis for deployment of advanced light water reactors (LWRs) and fast burner reactors, as proposed by the Global Nuclear Energy Partnership (GNEP) program. Conditions for the analysis were selected for their potential to challenge the nuclear fuel simulation codes that were used, due to the large variations in nuclear fuel composition for the burner reactors before equilibrium conditions are approached. The analysis was performed in a U.S.