You are here

Document Library

September 30, 2012
Advanced LWR Nuclear Fuel Cladding System Development Trade-off Study

The LWR Sustainability (LWRS) Program activities must support the timeline dictated by utility life extension decisions to demonstrate a lead test rod in a commercial reactor within 10 years. In order to maintain the demanding development schedule that must accompany this aggressive timeline, the LWRS Program focuses on advanced fuel cladding systems that retain standard UO2 fuel pellets for deployment in currently operating LWR power plants.

September 30, 2012
Guidance for Deployment of Mobile Technologies for Nuclear Power Plant Field Workers

This report is a guidance document prepared for the benefit of commercial nuclear power plants’ (NPPs) supporting organizations and personnel who are considering or undertaking deployment of mobile technology for the purpose of improving human performance and plant status control (PSC) for field workers in an NPP setting. This document especially is directed at NPP business managers, Electric Power Research Institute, Institute of Nuclear Power Operations, and other non-Information Technology personnel.

September 30, 2012
Light Water Reactor Sustainability Program: Materials Aging and Degradation Technical Program Plan

Components serving in a nuclear reactor plant must withstand a very harsh environment including extended time at temperature, neutron irradiation, stress, and/or corrosive media. The many modes of degradation are complex and vary depending on location and material. However, understanding and managing materials degradation is a key for the continued safe and reliable operation of nuclear power plants.

September 30, 2012
Summary Report on Industrial and Regulatory Engagement Activities

The Advanced Instrumentation, Information, and Control (II&C) Systems Technologies pathway of the Light Water Reactor Sustainability(LWRS) Program conducts a vigorous engagement strategy with the U.S. nuclear power industry, including the nuclear operating companies, major support organizations, the Nuclear Regulatory Commission (NRC), and suppliers.

September 30, 2012
Light Water Reactor Sustainability (LWRS) Program – R&D Roadmap for Non-Destructive Evaluation (NDE) of Fatigue Damage in Piping

Light water reactor sustainability (LWRS) nondestructive evaluation (NDE) Workshops were held at Oak Ridge National Laboratory (ORNL) during July 30th to August 2nd, 2012. This activity was conducted to help develop the content of the NDE R&D roadmap for the materials aging and degradation (MAaD) pathway of the LWRS program. The workshops focused on identifying NDE R&D needs in four areas: cables, concrete, reactor pressure vessel, and piping.

September 30, 2012
Light Water Reactor Sustainability Program – Non-Destructive Evaluation R&D Roadmap for Determining Remaining Useful Life of Aging Cables in Nuclear Power Plants

The purpose of the non-destructive evaluation (NDE) R&D Roadmap for Cables is to support the Materials Aging and Degradation (MAaD) R&D pathway. A workshop was held to gather subject matter experts to develop the NDE R&D Roadmap for Cables. The focus of the workshop was to identify the technical gaps in detecting aging cables and predicting their remaining life expectancy. The workshop was held in Knoxville, Tennessee, on July 30, 2012, at Analysis and Measurement Services Corporation (AMS) headquarters.

September 30, 2012
Roadmap for Nondestructive Evaluation of Reactor Pressure Vessel Research and Development by the Light Water Reactor Sustainability Program

The Department of Energy’s (DOE’s) Light Water Reactor Sustainability (LWRS) Program is a five year effort that works to develop the fundamental scientific basis to understand, predict, and measure changes in materials and systems, structure, and components as they age in environments associated with continued long-term operation of existing commercial nuclear power reactors. This year, the Materials Aging and Degradation (MAaD) Pathway of this program has placed emphasis on emerging nondestructive evaluation (NDE) methods that support these objectives.

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 30, 2012
Cast Stainless Steel Aging Research Plan

This work plan proposes to build a systematic knowledge base for the thermal aging behavior of cast stainless steels (CASSs) within a limited time of five years. The final output of execution of the plan is expected to provide conclusive predictions for the integrity of the CASS components of LWR power plants during the extended service life up to and beyond 60 years.

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.
 

September 28, 2012
Integrated Tool Development for Used Fuel Disposition Natural System Evaluation Phase I Report

The natural barrier system (NBS) is an integral part of a geologic nuclear waste repository. The report describes progress in development of an integrated modeling framework that can be used for systematically analyzing the performance of a natural barrier system and identifying key factors that control the performance. This framework is designed as an integrated tool for prioritization and programmatic decisions.

September 7, 2012
Integration of EBS Models with Generic Disposal System Models

This report summarizes research activities on engineered barrier system (EBS) model integration with the generic disposal system model (GDSM), and used fuel degradation and radionuclide mobilization (RM) in support of the EBS evaluation and tool development within the UFD campaign.

August 31, 2012
Research, Development, and Demonstration Roadmap for Deep Borehole Disposal

This roadmap is intended to advance deep borehole disposal (DBD) from its current conceptual status to potential future deployment as a disposal system for spent nuclear fuel (SNF) and high-level waste (HLW). The objectives of the DBD RD&D roadmap include providing the technical basis for fielding a DBD demonstration project, defining the scientific research activities associated with site characterization and postclosure safety, and defining the engineering demonstration activities associated with deep borehole drilling, completion, and surrogate waste canister emplacement.

August 30, 2012
Risk Informed Safety Margin Characterization (RISMC) Advanced Test Reactor Demonstration Case Study

Safety is central to the design, licensing, operation, and economics of Nuclear Power Plants (NPPs). Consequently, the ability to better characterize and quantify safety margin holds the key to improved decision making about light water reactor design, operation, and plant life extension. A systematic approach to characterization of safety margins and the subsequent margins management options represents a vital input to the licensee and regulatory analysis and decision making that will be involved.

August 30, 2012
Nuclear Power 2010 Program: Combined Construction and Operating License & Design Certification Demonstration Projects Lessons Learned Report

The Nuclear Power 2010 (NP 2010) Construction and Operating License/Design Certification (COL/DC) Demonstration program together with the financial incentives provided by the Energy Policy Act of 2005 are the two primary reasons why a number of license applications for new nuclear construction are before the NRC today, and why the first new nuclear plants in over 30 years are under construction in the United States.

August 30, 2012
Report on Modeling Coupled Processes in the Near Field of a Clay Repository

Clay/shale has been considered as potential host rock for geological disposal of high-level radioactive waste throughout the world. Coupled thermal, hydrological, mechanical, and chemical (THMC) processes have a significant impact on the long-term safety of a clay repository. This report documents results from three R&D activities: (1) implementation and validation of constitutive relationships, (2) development of a discrete fracture network (DFN) model for investigating coupled processes in the excavation damaged zone, and (3) development of a THM model for the Full-Scale Emplacement Experiment tests at Mont Terri, Switzerland, for the purpose of model validation. One major goal is to provide a better understanding of the evolution of the excavation damage zone in clay repositories.

July 31, 2012
Review of Used Nuclear Fuel Storage and Transportation Technical Gap Analysis

While both wet and dry storage have been shown to be safe options for storing UNF, the focus of the program is on dry storage of commercial UNF at reactor or centralized locations. This report focuses on the knowledge gaps concerning extended storage identified in numerous domestic and international investigations and provides the UFDC’s gap description, any alternate gap descriptions, the rankings by the various organizations, evaluation of the priority assignment, and UFDC-recommended action based on the comparison.

July 30, 2012
Influence of Nuclear Fuel Cycles on Uncertainty of Long Term Performance of Geologic Disposal Systems

Development and implementation of future advanced fuel cycles including those that recycle fuel materials, use advanced fuels different from current fuels, or partition and transmute actinide radionuclides, will impact the waste management system. The UFD Campaign can reasonably conclude that advanced fuel cycles, in combination with partitioning and transmutation, which remove actinides, will not materially alter the performance, the spread in dose results around the mean, the modeling effort to include significant features, events, and processes (FEPs) in the performance assessment, or the characterization of uncertainty associated with a geologic disposal system in the regulatory environment of the US.

July 30, 2012
NEUP Foreign Travel Request Form

NEUP Foreign Travel Request Form

July 30, 2012
Fuel Cycle Potential Waste Inventory for Disposition Rev 5

The United States (U.S.) currently utilizes a once-through fuel cycle where used nuclear fuel is stored onsite in either wet pools or in dry storage systems with ultimate disposal envisioned in a deep mined geologic repository. This report provides an estimate of potential waste inventory and waste form characteristics for the DOE UNF and HLW and a variety of commercial fuel cycle alternatives in order to support subsequent system-level evaluations of disposal system performance.

July 2, 2012
Quarterly Nuclear Deployment Scorecard - July 2012

The scorecard includes news updates, regulatory status, reactor design certification, early site permits, new plant construction progress, and new nuclear plants under construction.

July 1, 2012
NEAMS Quarterly Report April-June 2012

This Nuclear Energy Advanced Modeling and Simulation (NEAMS) quarterly report includes highlights, a spotlight on personal achievements, accomplishments, milestones and a technical spotlight on multiscale material model development for fuel performance codes.

June 30, 2012
Use Computational Model to Design and Optimize Welding Conditions to Suppress Helium Cracking during Welding

Today, welding is widely used for repair, maintenance and upgrade of nuclear reactor components. As a critical technology to extend the service life of nuclear power plants beyond 60 years, weld technology must be further developed to meet new challenges associated with the aging of the plants, such as control and mitigation of the detrimental effects of weld residual stresses and repair of highly irradiated materials. To meet this goal, fundamental understanding

June 30, 2012
Managing Aging Effects on Dry Cask Storage Systems for Extended Long Term Storage and Transportation of Used Fuel Rev0

The report is intended to help assess and establish the technical basis for extended long‐term storage and transportation of used nuclear fuel.  It provides: 1) an overview of the ISFSI license renewal process based on 10 CFR 72 and the guidance provided in NUREG‐1927; 2) definitions and terms for structures and components in DCSSs, materials, environments, aging effects, and aging mechanisms; 3) TLAAs and AMPs, respectively, that have been developed for managing aging effects on the SSCs important to safety in the dry cask storage system designs; and 4) AMPs and TLAAs for the SSCs that ar