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Used Fuel Disposition R&D Documents

September 30, 2013
Used Nuclear Fuel Loading and Structural Performance Under Normal Conditions of Transport – Demonstration of Approach and Results of Used Fuel Performance Characterization

This report provides results of the initial demonstration of the modeling capability developed to perform preliminary deterministic evaluations of moderate-to-high burnup used nuclear fuel (UNF) mechanical performance under normal conditions of storage (NCS) and transport (NCT).

September 30, 2013
FY 2013 Summary Report: Post-Irradiation Examination of Zircaloy-4 Samples in Target Capsules and Initiation of Bending Fatigue Testing for Used Nuclear Fuel Vibration Integrity Investigations

This study contributes to investigation and better understanding of cladding (High Flux Isotope Reactor used to simulate the effects of high burnup on fuel cladding) materials performance in extended storage and transportation through the conduct of small scale and separate effects tests (SET).

September 27, 2013
EBS Model Development and Evaluation Report

Enginerred Barrier Systems (EBS) model evaluation and development is fundamental to the design and analysis of disposal concepts for generic repository systems; this report centers on progress made on modeling and experimental approaches to analyze physical and chemical interactions affecting clay barrier performance.

September 25, 2013
Brine Migration Experimental Studies for Salt Repositories

Experiments were used to examine water content in Permian salt samples including impact of variation in thermal regime on water content of evaporites and other mineral species, behavior of brine inclusions in salt, and evolution of the gas/liquid brine/salt system.

September 15, 2013
Experimental and Modeling Investigation of Radionuclide Interaction and Transport in Representative Geologic Media

This work on the natural barrier system is conducted to reduce uncertainty in natural system performance and to fully exploit the credits that can be taken for the natural system barrier; several potential enhancements to describing barrier performance capabilities are presented.

August 30, 2013
Model for Simulation of Hydride Precipitation in Zr-Based Used Fuel Claddings: A Status Report on Current Model Capabilities

The report demonstrates a meso-scale, microstructural evolution model for simulation of zirconium hydride precipitation in the cladding of used fuels during long-term dry-storage.

August 30, 2013
Report on THMC Modeling of the Near Field Evolution of a Generic Clay Repository: Model Validation and Demonstration Rev 2

Shale and clay-rich rock formations have been considered as potential host rocks for geological disposal of high-level radioactive waste throughout the world: modeling thermal, hydrological, mechanical, and chemical (THMC) of the near field of generic clay repository is discussed.

August 14, 2013
Generic Deep Geologic Disposal Safety Case

The Generic Deep Geologic Disposal Safety Case presents generic information that is of use in understanding potential deep geologic disposal options (e.g., salt, shale, granite, deep borehole) in the U.S. for used nuclear fuel (UNF) from reactors and high-level radioactive waste (HLW).

July 29, 2013
Establishing the Technical Basis for Disposal of Heat-generating Waste in Salt

The report summarizes available historic tests and the developed technical basis for disposal of heat-generating waste in salt, and the means by which a safety case for disposal of heat generating waste at a generic salt site can be initiated from the existing technical basis.

June 30, 2013
Fuel Assembly Shaker Test for Determining Loads on a PWR Assembly under Surrogate Normal Conditions of Truck Transport R0.1

Results of testing employing surrogate instrumented rods (non-high-burnup, 17 x 17 PWR fuel assembly) to capture the response to the loadings experienced during normal conditions of transport indicate that strain- or stress-based failure of fuel rods seems unlikely; performance of high-burnup fuels continues to be assessed.

May 31, 2013
RD&D Study Plan for Advancement of Science and Engineering Supporting Geologic Disposal in Bedded Salt— March 2013 Workshop Outcomes

This report describes RD&D activities to support a safety case for disposal of heat generating radioactive waste (used nuclear fuel, high-level nuclear waste) in a generic bedded salt repository based on interactions from March, 2013 Workshop.

April 30, 2013
Hydride Rim Formation in Unirradiated Zircaloy

The purpose of this work is to develop the means of pre-hydriding unirradiated Zircaloy cladding such that a high concentration, or rim, of hydrides is formed at the cladding outside diameter.

April 30, 2013
Viability of Existing INL Facilities for Dry Storage Cask Handling R1

This report evaluates existing capabilities at Idaho National Laboratory (INL) to determine if a practical and cost effective method could be developed for handling and opening full-sized dry storage casks in support of the U.S. Department of Energy's plan for confirmatory dry storage project for high burnup fuel.

April 1, 2013
Used Nuclear Fuel Loading and Structural Performance Under Normal Conditions of Transport - Modeling, Simulation and Experimental Integration RD&D Plan

Used nuclear fuel (UNF) must maintain its integrity during the storage period in such a way that it can withstand the physical forces of handling and transportation associated with restaging the fuel and transporting it to treatment or recycling facilities, or to a geologic repository.

February 14, 2013
Proceedings of 3rd US/German Workshop on Salt Repository Research, Design, and Operation

The report provides summary and materials from the third U.S./German Workshop on Salt Repository Research, Design and Operation (held in New Mexico, October 2012).

December 30, 2012
Fluid Flow Model Development for Representative Geologic Media

Clay and granitic geologic rock units are potential host media for future repositories for used nuclear fuel and high level waste. This report addresses the representation of flow in these two media within numerical process (discrete fracture network) models.

December 30, 2012
Categorization of Used Nuclear Fuel Inventory in Support of a Comprehensive National Nuclear Fuel Cycle Strategy

The Office of Nuclear Energy has conducted a technical review and assessment of the total current inventory [~70,150 MTHM as of 2011] of domestic discharged used nuclear fuel (UNF) and estimated an amount to be considered for retention in support of research, development, demonstration, and national security interests.

November 30, 2012
Repository Reference Disposal Concepts and Thermal Load Management Analysis

A disposal concept consists of three parts: waste inventory (7 waste types examined), geologic setting (e.g., clay/shale, salt, crystalline, other sedimentary), and the engineering concept of operations (range of generic operational concepts examined; enclosed and open mode disposal concepts, thermal analysis, other).

November 15, 2012
Coupled Thermal-Hydrological-Mechanical Processes in Salt, Hot Granular Salt Consolidation, Constitutive Model and Micromechanics

The report addresses granular salt reconsolidation from three vantage points: laboratory testing, modeling, and petrofabrics.

September 30, 2012
Used Fuel Disposition Campaign Disposal Research and Development Roadmap Rev. 01

The Used Fuel Disposition Campaign (UFDC) conducts R&D activities related to storage, transportation and disposal of used nuclear fuel and high level nuclear waste (for existing and future fuels); deep geologic disposal R&D activities are outlined and prioritized on the basis of gaps in understanding and benefit derived from R&D to narrow such gaps.

September 30, 2012
Update of the Used Fuel Disposition Campaign Implementation Plan

The Used Fuel Disposition Campaign will identify alternatives and conduct scientific research and technology development to enable storage, transportation, and disposal of used nuclear fuel and wastes generated by existing and future nuclear fuel cycles.

September 30, 2012
Transportation Issues and Resolutions Compilation of Laboratory Transportation Work Package Reports

The Transportation Team identified the retrievability and subcriticality safety functions to be of primary importance to the transportation of UNF after extended storage and to transportation of high burnup fuel. The tasks performed and described herein address issues related to retrievability and subcriticality; integrity of cladding (embrittled, high burnup cladding, loads applied to cladding during transport), criticality analyses of failed UNF within transport packages, moderator exclusion concepts, stabilization of cladding with canisters for criticality control; and the need for maintaining a detailed inventory of UNF in dry storage as an ongoing activity.

September 30, 2012
Status of UFD Campaign International Activities in Disposal Research

Several international organizations have made significant progress in the characterization and performance evaluation of other disposal design options and host rock characteristics (clay/shale, granite), most of which were very different from those studied in the U.S. The DOE recognizes that close international collaboration is a beneficial and costeffective strategy for advancing disposal science. This report describes the active collaboration opportunities available to U.S. researchers, and presents specific cooperative research activities that have been recently initiated within DOE’s disposal research program.

September 28, 2012
TSPA Model Development and Sensitivity Analysis of Processes Affecting Performance of a Salt Repository for Disposal of Heat-Generating Nuclear Waste

The document describes the initial work on designing and developing requirements for a total system performance assessment (TSPA) model that can support preliminary safety assessments for a mined geologic repository for high-level waste (HLW) and spent nuclear fuel (SNF) in salt host rock at a generic site. A preliminary generic salt TSPA model for HLW/SNF disposal has been developed and tested for an isothermal repository in salt, for emplaced waste that is assumed to have no decay heat; for salt repositories containing heat-generating HLW/SNF, the present study develops model requirements based on features, events, and processes (FEPs) screening and proposed sensitivity analyses for heat-generating waste. These may better guide the construction of a more representative salt TSPA model.

September 28, 2012
Model Development and Analysis of the Fate and Transport of Water in a Salt Based Repository

The study summarizes the initial work on numerical modeling, simulations, and experimental results related to nuclear waste storage in a salt repository.  The study reflects the project's preliminary effort at simulating the fluid flow and heat transport processes, before treating the fully coupled thermal-mechanical-hydrologic-chemical (TMHC) coupled processes in the future.