Sample records for reactor sustainability program

  1. LIGHT WATER REACTOR SUSTAINABILITY PROGRAM: INTRODUCTION

    Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

    LIGHT WATER REACTOR SUSTAINABILITY PROGRAM: INTRODUCTION The Light Water Reactor Sustainability (LWRS) Program is the primary programmatic activity that addresses Objective 1...

  2. Light Water Reactor Sustainability (LWRS) Program

    Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

    Light Water Reactor Sustainability (LWRS) Program Login Instructions go here. User ID: Password: Log In Forgot your password?...

  3. Light Water Reactor Sustainability Program - Non-Destructive...

    Energy Savers [EERE]

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

  4. Light Water Reactor Sustainability Program Contact Information

    Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

    Program Organization LWRS Program Management Richard Reister Federal Project Director Light Water Reactor Deployment Office of Nuclear Energy U.S. Department of Energy...

  5. Light Water Reactor Sustainability

    Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

    3 Light Water Reactor Sustainability Program ACCOMPLISHMENTS REPORT 2013 Accomplishments Report | Light Water Reactor Sustainability 2 T he mission of the Light Water Reactor...

  6. LWR Sustainability Program Documents

    Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

    References LWRS Program Reports Technical Integration Office Light Water Reactor Sustainability Program Accomplishments Report, 2014. pdf Light Water Reactor Sustainability...

  7. Light Water Reactor Sustainability Program Integrated Program Plan

    SciTech Connect (OSTI)

    McCarthy, Kathryn A. [INL; Busby, Jeremy [ORNL; Hallbert, Bruce [INL; Bragg-Sitton, Shannon [INL; Smith, Curtis [INL; Barnard, Cathy [INL

    2014-04-01T23:59:59.000Z

    Nuclear power has safely, reliably, and economically contributed almost 20% of electrical generation in the United States over the past two decades. It remains the single largest contributor (more than 70%) of non-greenhouse-gas-emitting electric power generation in the United States. Domestic demand for electrical energy is expected to experience a 31% growth from 2009 to 2035. At the same time, most of the currently operating nuclear power plants will begin reaching the end of their initial 20-year extension to their original 40-year operating license for a total of 60 years of operation. Figure E-1 shows projected nuclear energy contribution to the domestic generating capacity. If current operating nuclear power plants do not operate beyond 60 years, the total fraction of generated electrical energy from nuclear power will begin to decline—even with the expected addition of new nuclear generating capacity. The oldest commercial plants in the United States reached their 40th anniversary in 2009. The U.S. Department of Energy Office of Nuclear Energy’s Research and Development Roadmap (Nuclear Energy Roadmap) organizes its activities around four objectives that ensure nuclear energy remains a compelling and viable energy option for the United States. The four objectives are as follows: (1) develop technologies and other solutions that can improve the reliability, sustain the safety, and extend the life of the current reactors; (2) develop improvements in the affordability of new reactors to enable nuclear energy to help meet the Administration’s energy security and climate change goals; (3) develop sustainable nuclear fuel cycles; and (4) understand and minimize the risks of nuclear proliferation and terrorism. The Light Water Reactor Sustainability (LWRS) Program is the primary programmatic activity that addresses Objective 1. This document summarizes the LWRS Program’s plans.

  8. Light Water Reactor Sustainability Program Integrated Program Plan

    SciTech Connect (OSTI)

    Kathryn McCarthy; Jeremy Busby; Bruce Hallbert; Shannon Bragg-Sitton; Curtis Smith; Cathy Barnard

    2013-04-01T23:59:59.000Z

    Nuclear power has safely, reliably, and economically contributed almost 20% of electrical generation in the United States over the past two decades. It remains the single largest contributor (more than 70%) of non-greenhouse-gas-emitting electric power generation in the United States. Domestic demand for electrical energy is expected to experience a 31% growth from 2009 to 2035. At the same time, most of the currently operating nuclear power plants will begin reaching the end of their initial 20-year extension to their original 40-year operating license for a total of 60 years of operation. Figure E-1 shows projected nuclear energy contribution to the domestic generating capacity. If current operating nuclear power plants do not operate beyond 60 years, the total fraction of generated electrical energy from nuclear power will begin to decline—even with the expected addition of new nuclear generating capacity. The oldest commercial plants in the United States reached their 40th anniversary in 2009. The U.S. Department of Energy Office of Nuclear Energy’s Research and Development Roadmap (Nuclear Energy Roadmap) organizes its activities around four objectives that ensure nuclear energy remains a compelling and viable energy option for the United States. The four objectives are as follows: (1) develop technologies and other solutions that can improve the reliability, sustain the safety, and extend the life of the current reactors; (2) develop improvements in the affordability of new reactors to enable nuclear energy to help meet the Administration’s energy security and climate change goals; (3) develop sustainable nuclear fuel cycles; and (4) understand and minimize the risks of nuclear proliferation and terrorism. The Light Water Reactor Sustainability (LWRS) Program is the primary programmatic activity that addresses Objective 1. This document summarizes the LWRS Program’s plans.

  9. Light Water Reactor Sustainability Program Integrated Program Plan

    SciTech Connect (OSTI)

    George Griffith; Robert Youngblood; Jeremy Busby; Bruce Hallbert; Cathy Barnard; Kathryn McCarthy

    2012-01-01T23:59:59.000Z

    Nuclear power has safely, reliably, and economically contributed almost 20% of electrical generation in the United States over the past two decades. It remains the single largest contributor (more than 70%) of non-greenhouse-gas-emitting electric power generation in the United States. Domestic demand for electrical energy is expected to experience a 31% growth from 2009 to 2035. At the same time, most of the currently operating nuclear power plants will begin reaching the end of their initial 20-year extension to their original 40-year operating license for a total of 60 years of operation. Figure E-1 shows projected nuclear energy contribution to the domestic generating capacity. If current operating nuclear power plants do not operate beyond 60 years, the total fraction of generated electrical energy from nuclear power will begin to decline - even with the expected addition of new nuclear generating capacity. The oldest commercial plants in the United States reached their 40th anniversary in 2009. The U.S. Department of Energy Office of Nuclear Energy's Research and Development Roadmap (Nuclear Energy Roadmap) organizes its activities around four objectives that ensure nuclear energy remains a compelling and viable energy option for the United States. The four objectives are as follows: (1) develop technologies and other solutions that can improve the reliability, sustain the safety, and extend the life of the current reactors; (2) develop improvements in the affordability of new reactors to enable nuclear energy to help meet the Administration's energy security and climate change goals; (3) develop sustainable nuclear fuel cycles; and (4) understand and minimize the risks of nuclear proliferation and terrorism. The Light Water Reactor Sustainability (LWRS) Program is the primary programmatic activity that addresses Objective 1. This document summarizes the LWRS Program's plans.

  10. Materials Inventory Database for the Light Water Reactor Sustainability Program

    SciTech Connect (OSTI)

    Kazi Ahmed; Shannon M. Bragg-Sitton

    2013-08-01T23:59:59.000Z

    Scientific research involves the purchasing, processing, characterization, and fabrication of many sample materials. The history of such materials can become complicated over their lifetime – materials might be cut into pieces or moved to various storage locations, for example. A database with built-in functions to track these kinds of processes facilitates well-organized research. The Material Inventory Database Accounting System (MIDAS) is an easy-to-use tracking and reference system for such items. The Light Water Reactor Sustainability Program (LWRS), which seeks to advance the long-term reliability and productivity of existing nuclear reactors in the United States through multiple research pathways, proposed MIDAS as an efficient way to organize and track all items used in its research. The database software ensures traceability of all items used in research using built-in functions which can emulate actions on tracked items – fabrication, processing, splitting, and more – by performing operations on the data. MIDAS can recover and display the complete history of any item as a simple report. To ensure the database functions suitably for the organization of research, it was developed alongside a specific experiment to test accident tolerant nuclear fuel cladding under the LWRS Advanced Light Water Reactor Nuclear Fuels Pathway. MIDAS kept track of materials used in this experiment from receipt at the laboratory through all processes, test conduct and, ultimately, post-test analysis. By the end of this process, the database proved to be right tool for this program. The database software will help LWRS more efficiently conduct research experiments, from simple characterization tests to in-reactor experiments. Furthermore, MIDAS is a universal tool that any other research team could use to organize their material inventory.

  11. Light Water Reactor Sustainability

    Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

    4 Light Water Reactor Sustainability ACCOMPLISHMENTS REPORT 2014 Accomplishments Report | Light Water Reactor Sustainability 2 T he mission of the Light Water Reactor...

  12. INL/EXT-14-33257 Light Water Reactor Sustainability Program

    Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

    57 Light Water Reactor Sustainability Program 3D J-Integral Capability in Grizzly September 2014 DOE Office of Nuclear Energy DISCLAIMER This information was prepared as an account...

  13. REACTOR PRESSURE VESSEL ISSUES FOR THE LIGHT-WATER REACTOR SUSTAINABILITY PROGRAM

    SciTech Connect (OSTI)

    Nanstad, Randy K [ORNL; Odette, George Robert [UCSB

    2010-01-01T23:59:59.000Z

    The Light Water Reactor Sustainability Program Plan is a collaborative program between the U.S. Department of Energy and the private sector directed at extending the life of the present generation of nuclear power plants to enable operation to at least 80 years. The reactor pressure vessel (RPV) is one of the primary components requiring significant research to enable such long-term operation. There are significant issues that need to be addressed to reduce the uncertainties in regulatory application, such as, 1) high neutron fluence/long irradiation times, and flux effects, 2) material variability, 3) high-nickel materials, 4)specimen size effects and the fracture toughness master curve, etc. The first issue is the highest priority to obtain the data and mechanistic understanding to enable accurate, reliable embrittlement predictions at high fluences. This paper discusses the major issues associated with long-time operation of existing RPVs and the LWRSP plans to address those issues.

  14. Light Water Reactor Sustainability Newsletter

    Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

    hydraulics software RELAP-7 (which is under development in the Light Water Reactor Sustainability LWRS Program). A novel interaction between the probabilistic part (i.e., RAVEN)...

  15. Overview of the US Department of Energy Light Water Reactor Sustainability Program

    SciTech Connect (OSTI)

    K. A. McCarthy; D. L. Williams; R. Reister

    2012-05-01T23:59:59.000Z

    The US Department of Energy Light Water Reactor Sustainability Program is focused on the long-term operation of US commercial power plants. It encompasses two facets of long-term operation: (1) manage the aging of plant systems, structures, and components so that nuclear power plant lifetimes can be extended and the plants can continue to operate safely, efficiently, and economically; and (2) provide science-based solutions to the nuclear industry that support implementation of performance improvement technologies. An important aspect of the Light Water Reactor Sustainability Program is partnering with industry and the Nuclear Regulatory Commission to support and conduct the long-term research needed to inform major component refurbishment and replacement strategies, performance enhancements, plant license extensions, and age-related regulatory oversight decisions. The Department of Energy research, development, and demonstration role focuses on aging phenomena and issues that require long-term research and/or unique Department of Energy laboratory expertise and facilities and are applicable to all operating reactors. This paper gives an overview of the Department of Energy Light Water Reactor Sustainability Program, including vision, goals, and major deliverables.

  16. Light Water Reactor Sustainability (LWRS) Program | Department of Energy

    Broader source: Energy.gov (indexed) [DOE]

    AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE:1 First Use of Energy for All Purposes (Fuel and Nonfuel),Feet) Year Jan Feb Mar Apr May Jun Jul(Summary) "of EnergyEnergyENERGYWomen OwnedofDepartment ofJared Temanson -of Energy 1procedures,Light Water Reactor

  17. Roadmap for Nondestructive Evaluation of Reactor Pressure Vessel Research and Development by the Light Water Reactor Sustainability Program

    SciTech Connect (OSTI)

    Smith, Cyrus M [ORNL; Nanstad, Randy K [ORNL; Clayton, Dwight A [ORNL; Matlack, Katie [Georgia Institute of Technology; Ramuhalli, Pradeep [Pacific Northwest National Laboratory (PNNL); Light, Glenn [Southwest Research Institute, San Antonio

    2012-09-01T23:59:59.000Z

    The Department of Energy s (DOE) Light Water Reactor Sustainability (LWRS) Program is a five year effort which 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 operations of existing commercial nuclear power reactors. This year, the Materials Aging and Degradation (MAaD) Pathway of this program has placed emphasis on emerging Non-Destructive Evaluation (NDE) methods which support these objectives. DOE funded Research and Development (R&D) on emerging NDE techniques to support commercial nuclear reactor sustainability is expected to begin next year. This summer, the MAaD Pathway invited subject matter experts to participate in a series of workshops which developed the basis for the research plan of these DOE R&D NDE activities. This document presents the results of one of these workshops which are the DOE LWRS NDE R&D Roadmap for Reactor Pressure Vessels (RPV). These workshops made a substantial effort to coordinate the DOE NDE R&D with that already underway or planned by the Electric Power Research Institute (EPRI) and the Nuclear Regulatory Commission (NRC) through their representation at these workshops.

  18. Light Water Reactor Sustainability Program Status of Silicon Carbide Joining Technology Development

    SciTech Connect (OSTI)

    Shannon M. Bragg-Sitton

    2013-09-01T23:59:59.000Z

    Advanced, accident tolerant nuclear fuel systems are currently being investigated for potential application in currently operating light water reactors (LWR) or in reactors that have attained design certification. Evaluation of potential options for accident tolerant nuclear fuel systems point to the potential benefits of silicon carbide (SiC) relative to Zr-based alloys, including increased corrosion resistance, reduced oxidation and heat of oxidation, and reduced hydrogen generation under steam attack (off-normal conditions). If demonstrated to be applicable in the intended LWR environment, SiC could be used in nuclear fuel cladding or other in-core structural components. Achieving a SiC-SiC joint that resists corrosion with hot, flowing water, is stable under irradiation and retains hermeticity is a significant challenge. This report summarizes the current status of SiC-SiC joint development work supported by the Department of Energy Light Water Reactor Sustainability Program. Significant progress has been made toward SiC-SiC joint development for nuclear service, but additional development and testing work (including irradiation testing) is still required to present a candidate joint for use in nuclear fuel cladding.

  19. Light Water Reactor Sustainability Research and Development Program Plan -- Fiscal Year 2009–2013

    SciTech Connect (OSTI)

    Idaho National Laboratory

    2009-12-01T23:59:59.000Z

    Nuclear power has reliably and economically contributed almost 20% of electrical generation in the United States over the past two decades. It remains the single largest contributor (more than 70%) of non-greenhouse-gas-emitting electric power generation in the United States. By the year 2030, domestic demand for electrical energy is expected to grow to levels of 16 to 36% higher than 2007 levels. At the same time, most currently operating nuclear power plants will begin reaching the end of their 60-year operating licenses. If current operating nuclear power plants do not operate beyond 60 years, the total fraction of generated electrical energy from nuclear power will begin to decline—even with the expected addition of new nuclear generating capacity. The oldest commercial plants in the United States reached their 40th anniversary this year. U.S. regulators have begun considering extended operations of nuclear power plants and the research needed to support long-term operations. The Light Water Reactor Sustainability (LWRS) Research and Development (R&D) Program, developed and sponsored by the Department of Energy, is performed in close collaboration with industry R&D programs. The purpose of the LWRS R&D Program is to provide technical foundations for licensing and managing long-term, safe and economical operation of the current operating nuclear power plants. The LWRS R&D Program vision is captured in the following statements: Existing operating nuclear power plants will continue to safely provide clean and economic electricity well beyond their first license- extension period, significantly contributing to reduction of United States and global carbon emissions, enhancement of national energy security, and protection of the environment. There is a comprehensive technical basis for licensing and managing the long-term, safe, economical operation of nuclear power plants. Sustaining the existing operating U.S. fleet also will improve its international engagement and leadership on nuclear safety and security issues.

  20. Light Water Reactor Sustainability Program A Reference Plan for Control Room Modernization: Planning and Analysis Phase

    SciTech Connect (OSTI)

    Jacques Hugo; Ronald Boring; Lew Hanes; Kenneth Thomas

    2013-09-01T23:59:59.000Z

    The U.S. Department of Energy’s Light Water Reactor Sustainability (LWRS) program is collaborating with a U.S. nuclear utility to bring about a systematic fleet-wide control room modernization. To facilitate this upgrade, a new distributed control system (DCS) is being introduced into the control rooms of these plants. The DCS will upgrade the legacy plant process computer and emergency response facility information system. In addition, the DCS will replace an existing analog turbine control system with a display-based system. With technology upgrades comes the opportunity to improve the overall human-system interaction between the operators and the control room. To optimize operator performance, the LWRS Control Room Modernization research team followed a human-centered approach published by the U.S. Nuclear Regulatory Commission. NUREG-0711, Rev. 3, Human Factors Engineering Program Review Model (O’Hara et al., 2012), prescribes four phases for human factors engineering. This report provides examples of the first phase, Planning and Analysis. The three elements of Planning and Analysis in NUREG-0711 that are most crucial to initiating control room upgrades are: • Operating Experience Review: Identifies opportunities for improvement in the existing system and provides lessons learned from implemented systems. • Function Analysis and Allocation: Identifies which functions at the plant may be optimally handled by the DCS vs. the operators. • Task Analysis: Identifies how tasks might be optimized for the operators. Each of these elements is covered in a separate chapter. Examples are drawn from workshops with reactor operators that were conducted at the LWRS Human System Simulation Laboratory HSSL and at the respective plants. The findings in this report represent generalized accounts of more detailed proprietary reports produced for the utility for each plant. The goal of this LWRS report is to disseminate the technique and provide examples sufficient to serve as a template for other utilities’ projects for control room modernization.

  1. Light Water Reactor Sustainability Newsletter By John Gaertner

    Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

    Year 2011 LWRS Program funding is very clear: "Regarding the Light Water Reactor Sustainability program, (Congress) expects a high cost share from industry." Cost sharing is...

  2. Light Water Reactor Sustainability Program Grizzly Year-End Progress Report

    SciTech Connect (OSTI)

    Benjamin Spencer; Yongfeng Zhang; Pritam Chakraborty; S. Bulent Biner; Marie Backman; Brian Wirth; Stephen Novascone; Jason Hales

    2013-09-01T23:59:59.000Z

    The Grizzly software application is being developed under the Light Water Reactor Sustainability (LWRS) program to address aging and material degradation issues that could potentially become an obstacle to life extension of nuclear power plants beyond 60 years of operation. Grizzly is based on INL’s MOOSE multiphysics simulation environment, and can simultaneously solve a variety of tightly coupled physics equations, and is thus a very powerful and flexible tool with a wide range of potential applications. Grizzly, the development of which was begun during fiscal year (FY) 2012, is intended to address degradation in a variety of critical structures. The reactor pressure vessel (RPV) was chosen for an initial application of this software. Because it fulfills the critical roles of housing the reactor core and providing a barrier to the release of coolant, the RPV is clearly one of the most safety-critical components of a nuclear power plant. In addition, because of its cost, size and location in the plant, replacement of this component would be prohibitively expensive, so failure of the RPV to meet acceptance criteria would likely result in the shutting down of a nuclear power plant. The current practice used to perform engineering evaluations of the susceptibility of RPVs to fracture is to use the ASME Master Fracture Toughness Curve (ASME Code Case N-631 Section III). This is used in conjunction with empirically based models that describe the evolution of this curve due to embrittlement in terms of a transition temperature shift. These models are based on an extensive database of surveillance coupons that have been irradiated in operating nuclear power plants, but this data is limited to the lifetime of the current reactor fleet. This is an important limitation when considering life extension beyond 60 years. The currently available data cannot be extrapolated with confidence further out in time because there is a potential for additional damage mechanisms (i.e. late blooming phases) to become active later in life beyond the current operational experience. To develop a tool that can eventually serve a role in decision-making, it is clear that research and development must be perfomed at multiple scales. At the engineering scale, a multiphysics analysis code that can capture the thermomechanical response of the RPV under accident conditions, including detailed fracture mechanics evaluations of flaws with arbitrary geometry and orientation, is needed to assess whether the fracture toughness, as defined by the master curve, including the effects of embrittlement, is exceeded. At the atomistic scale, the fundamental mechanisms of degradation need to be understood, including the effects of that degradation on the relevant material properties. In addition, there is a need to better understand the mechanisms leading to the transition from ductile to brittle fracture through improved continuum mechanics modeling at the fracture coupon scale. Work is currently being conducted at all of these levels with the goal of creating a usable engineering tool informed by lower length-scale modeling. This report summarizes progress made in these efforts during FY 2013.

  3. Light Water Reactor Sustainability Newsletter

    Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

    30-35, August 2012. Clayton, D. A. and M. S. Hileman, 2012, Light Water Reactor Sustainability Non-Destructive Evaluation for Concrete Research and Development Roadmap, ORNLTM-...

  4. Light Water Reactor Sustainability Newsletter Kathryn McCarthy

    Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

    Technical Integration Office T he Light Water Reactor Sustainability (LWRS) Pro- gram Integrated Program Plan was released on January 31, 2012; it can be downloaded at https:...

  5. Light Water Reactor Sustainability Newsletter By Rich Reister

    Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

    the safety, and extend the life of current reactors. The Light Water Re- actor Sustainability (LWRS) program is NE's principal means of achieving this objective. We have...

  6. Light Water Reactor Sustainability Newsletter Thomas M. Rosseel

    Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

    Laboratory (ORNL), through the Department of Energy's (DOE) Light Water Reactor Sustainability (LWRS) Program, is coordinating and contracting with Zion Solutions, LLC (a...

  7. Light Water Reactor Sustainability Program Risk Informed Safety Margin Characterization (RISMC) Advanced Test Reactor Demonstration Case Study

    SciTech Connect (OSTI)

    Curtis Smith; David Schwieder; Cherie Phelan; Anh Bui; Paul Bayless

    2012-08-01T23:59:59.000Z

    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 LWR 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. The purpose of the RISMC Pathway R&D is to support plant decisions for risk-informed margins management with the aim to improve economics, reliability, and sustain safety of current NPPs. Goals of the RISMC Pathway are twofold: (1) Develop and demonstrate a risk-assessment method coupled to safety margin quantification that can be used by NPP decision makers as part of their margin recovery strategies. (2) Create an advanced “RISMC toolkit” that enables more accurate representation of NPP safety margin. This report describes the RISMC methodology demonstration where the Advanced Test Reactor (ATR) was used as a test-bed for purposes of determining safety margins. As part of the demonstration, we describe how both the thermal-hydraulics and probabilistic safety calculations are integrated and used to quantify margin management strategies.

  8. Light Water Reactor Sustainability Newsletter Kathryn A. McCarthy

    Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

    S ome of the Light Water Reactor Sustainability (LWRS) Program managers have changed; therefore, I would like to provide a brief introduction to all of the LWRS program managers:...

  9. Sustainable Agriculture Loan Program

    Broader source: Energy.gov [DOE]

    The Minnesota Sustainable Agriculture Loan program will provide loans to Minnesota residents actively engaged in farming for capital expenditures which enhance the environmental and economic...

  10. Sustainable Energy Management Programs

    E-Print Network [OSTI]

    Hanner, S.

    2014-01-01T23:59:59.000Z

    Sustainable Energy Management Programs Steve Hanner Allen ISD/TEMA . ESL-KT-14-11-45 CATEE 2014: Clean Air Through Efficiency Conference, Dallas, Texas Nov. 18-20 Starting an Energy Management Program • Recognize need, Elicit District Commitment... • Appoint Energy Manager • Analyze Existing Conditions • Develop Plan • Implement and Monitor Program ESL-KT-14-11-45 CATEE 2014: Clean Air Through Efficiency Conference, Dallas, Texas Nov. 18-20 Sustainable Programs Feature – District Commitment...

  11. Light Water Reactor Sustainability Program FY13 Status Update for EPRI - RISMC Collaboration

    SciTech Connect (OSTI)

    Curtis Smith

    2013-09-01T23:59:59.000Z

    The purpose of the Risk Informed Safety Margin Characterization (RISMC) Pathway research and development (R&D) is to support plant decisions for risk-informed margins management with the aim to improve economics, reliability, and sustain safety of current NPPs. Goals of the RISMC Pathway are twofold: (1) Develop and demonstrate a risk-assessment method coupled to safety margin quantification that can be used by NPP decision makers as part of their margin recovery strategies. (2) Create an advanced "RISMC toolkit" that enables more accurate representation of NPP safety margin. In order to carry out the R&D needed for the Pathway, the Idaho National Laboratory (INL) is collaborating with the Electric Power Research Institute (EPRI) in order to focus on applications of interest to the U.S. nuclear power industry. This report documents the collaboration activities performed between INL and EPRI during FY2013.

  12. DOE-NE Light Water Reactor Sustainability Program and EPRI Long-Term

    Energy Savers [EERE]

    AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative Fuels Data Center Home Page on Google Bookmark EERE: Alternative Fuels Data Center Home Page on Deliciouscritical_materials_workshop_presentations.pdf MoreProgramofContracttoAugust 05,0-1MarchOperations Program -

  13. Reactor Sharing Program

    SciTech Connect (OSTI)

    Vernetson, W.G.

    1993-01-01T23:59:59.000Z

    Progress achieved at the University of Florida Training Reactor (UFTR) facility through the US Department of Energy's University Reactor Sharing Program is reported for the period of 1991--1992.

  14. LIGHT WATER REACTOR SUSTAINABILITY PROGRAM ADVANCED INSTRUMENTATION, INFORMATION, AND CONTROL SYSTEMS TECHNOLOGIES TECHNICAL PROGRAM PLAN FOR 2013

    SciTech Connect (OSTI)

    Hallbert, Bruce; Thomas, Ken

    2014-07-01T23:59:59.000Z

    Reliable instrumentation, information, and control (II&C) systems technologies are essential to ensuring safe and efficient operation of the U.S. light water reactor (LWR) fleet. These technologies affect every aspect of nuclear power plant (NPP) and balance-of-plant operations. In 1997, the National Research Council conducted a study concerning the challenges involved in modernization of digital instrumentation and control systems in NPPs. Their findings identified the need for new II&C technology integration.

  15. Light Water Reactor Sustainability Program Risk-Informed Safety Margins Characterization (RISMC) PathwayTechnical Program Plan

    SciTech Connect (OSTI)

    Curtis Smith; Cristian Rabiti; Richard Martineau

    2012-11-01T23:59:59.000Z

    Safety is central to the design, licensing, operation, and economics of Nuclear Power Plants (NPPs). As the current Light Water Reactor (LWR) NPPs age beyond 60 years, there are possibilities for increased frequency of Systems, Structures, and Components (SSCs) degradations or failures that initiate safety-significant events, reduce existing accident mitigation capabilities, or create new failure modes. Plant designers commonly “over-design” portions of NPPs and provide robustness in the form of redundant and diverse engineered safety features to ensure that, even in the case of well-beyond design basis scenarios, public health and safety will be protected with a very high degree of assurance. This form of defense-in-depth is a reasoned response to uncertainties and is often referred to generically as “safety margin.” Historically, specific safety margin provisions have been formulated, primarily based on “engineering judgment.”

  16. Sustainable Transportation Program | Clean Energy | ORNL

    Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

    Program SHARE Sustainable Transportation Program Oak Ridge National Laboratory's Sustainable Transportation Program Office administratively facilitates the integration of...

  17. Self-Sustaining Thorium Boiling Water Reactors

    E-Print Network [OSTI]

    Ganda, Francesco

    A thorium-fueled water-cooled reactor core design approach that features a radially uniform composition of fuel rods in stationary fuel assembly and is fuel-self-sustaining is described. This core design concept is similar ...

  18. Reactor Safety Research Programs

    SciTech Connect (OSTI)

    Edler, S. K.

    1981-07-01T23:59:59.000Z

    This document summarizes the work performed by Pacific Northwest Laboratory (PNL) from January 1 through March 31, 1981, for the Division of Reactor Safety Research within the U.S. Nuclear Regulatory Commission (NRC). Evaluations of nondestructive examination (NDE) techniques and instrumentation are reported; areas of investigation include demonstrating the feasibility of determining the strength of structural graphite, evaluating the feasibility of detecting and analyzing flaw growth in reactor pressure boundary systems, examining NDE reliability and probabilistic fracture mechanics, and assessing the integrity of pressurized water reactor (PWR) steam generator tubes where service-induced degradation has been indicated. Experimental data and analytical models are being provided to aid in decision-making regarding pipeto- pipe impacts following postulated breaks in high-energy fluid system piping. Core thermal models are being developed to provide better digital codes to compute the behavior of full-scale reactor systems under postulated accident conditions. Fuel assemblies and analytical support are being provided for experimental programs at other facilities. These programs include loss-ofcoolant accident (LOCA) simulation tests at the NRU reactor, Chalk River, Canada; fuel rod deformation, severe fuel damage, and postaccident coolability tests for the ESSOR reactor Super Sara Test Program, Ispra, Italy; the instrumented fuel assembly irradiation program at Halden, Norway; and experimental programs at the Power Burst Facility, Idaho National Engineering Laboratory (INEL). These programs will provide data for computer modeling of reactor system and fuel performance during various abnormal operating conditions.

  19. Program Sustainability: Incorporating Energy Efficiency into...

    Broader source: Energy.gov (indexed) [DOE]

    Program Sustainability: Incorporating Energy Efficiency into Disaster Recovery Efforts Peer Exchange Call Program Sustainability: Incorporating Energy Efficiency into Disaster...

  20. Program Sustainability: Coordinating Energy Efficiency with Water...

    Broader source: Energy.gov (indexed) [DOE]

    Program Sustainability: Coordinating Energy Efficiency with Water Conservation Services Peer Exchange Call Program Sustainability: Coordinating Energy Efficiency with Water...

  1. Reactor Safety Research Programs

    SciTech Connect (OSTI)

    Dotson, CW

    1980-08-01T23:59:59.000Z

    This document summarizes the work performed by Pacific Northwest laboratory from October 1 through December 31, 1979, for the Division of Reactor Safety Research within the Nuclear Regulatory Commission. Evaluation of nondestructive examination (NDE) techniques and instrumentation are reported; areas of investigation include demonstrating the feasibilty of determining structural graphite strength, evaluating the feasibilty of detecting and analyzing flaw growth in reactor pressure boundary systems, examining NDE reliability and probabilistic fracture mechanics, and assessing the remaining integrity of pressurized water reactor steam generator tubes where service-induced degradation has been indicated. Test assemblies and analytical support are being provided for experimental programs at other facilities. These programs include the loss-of-coolant accident simulation tests at the NRU reactor, Chalk River, Canada; the fuel rod deformation and post-accident coolability tests for the ESSOR Test Reactor Program, lspra, Italy; the blowdown and reflood tests in the test facility at Cadarache, France; the instrumented fuel assembly irradiation program at Halden, Norway; and the experimental programs at the Power Burst Facility, Idaho National Engineering Laboratory. These programs will provide data for computer modeling of reactor system and fuel performance during various abnormal operating conditions.

  2. Light Water Reactor Sustainability Newsletter

    Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

    and nuclear waste disposal. Dr. Corradini has extensive research experience in the phenomenology of beyond design basis Meet the New LWRS Program Pathway Lead accidents in light...

  3. Light Water Reactor Sustainability Constellation Pilot Project FY11 Summary Report

    SciTech Connect (OSTI)

    R. Johansen

    2011-09-01T23:59:59.000Z

    Summary report for Fiscal Year 2011 activities associated with the Constellation Pilot Project. The project is a joint effor between Constellation Nuclear Energy Group (CENG), EPRI, and the DOE Light Water Reactor Sustainability Program. The project utilizes two CENG reactor stations: R.E. Ginna and Nine Point Unit 1. Included in the report are activities associate with reactor internals and concrete containments.

  4. EL Program: Sustainable Engineered Materials Program Manager: Aaron Forster, Division

    E-Print Network [OSTI]

    1 EL Program: Sustainable Engineered Materials Program Manager: Aaron Forster, Division Associate Program Manager: None Strategic Goal: Sustainable and Energy-Effic Infrastructure 731 ient Manufacturing used in infrastructure, construction, and manufacturing are not able to ensure sustainable performance

  5. Light Water Reactor Sustainability Program Support and Modeling for the Boiling Water Reactor Station Black Out Case Study Using RELAP and RAVEN

    SciTech Connect (OSTI)

    Diego Mandelli; Curtis Smith; Thomas Riley; John Schroeder; Cristian Rabiti; Aldrea Alfonsi; Joe Nielsen; Dan Maljovec; Bie Wang; Valerio Pascucci

    2013-09-01T23:59:59.000Z

    The existing fleet of nuclear power plants is in the process of extending its lifetime and increasing the power generated. In order to evaluate the impact of these two factors on the safety of the plant, the Risk Informed Safety Margin Characterization (RISMC) project aims to provide insight to decision makers through a series of simulations of the plant dynamics for different initial conditions (e.g., probabilistic analysis and uncertainty quantification). This report focuses, in particular, on the impact of power uprate on the safety of a boiled water reactor system. The case study considered is a loss of off-site power followed by the loss of diesel generators, i.e., a station black out (SBO) event. Analysis is performed by using a thermo-hydraulic code, i.e. RELAP-5, and a stochastic analysis tool currently under development at INL, i.e. RAVEN. Starting from the event tree models contained in SAPHIRE, we built the input file for RELAP-5 that models in great detail system dynamics under SBO conditions. We also interfaced RAVEN with RELAP-5 so that it would be possible to run multiple RELAP-5 simulation runs by changing specific keywords of the input file. We both employed classical statistical tools, i.e. Monte-Carlo, and more advanced machine learning based algorithms to perform uncertainty quantification in order to quantify changes in system performance and limitations as a consequence of power uprate. We also employed advanced data analysis and visualization tools that helped us to correlate simulation outcome such as maximum core temperature with a set of input uncertain parameters. Results obtained gave a detailed overview of the issues associated to power uprate for a SBO accident scenario. We were able to quantify how timing of safety related events were impacted by a higher reactor core power. Such insights can provide useful material to the decision makers to perform risk-infomed safety margins management.

  6. Sustainable Transportation Program | ornl.gov

    Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

    with government, industry, and academia, Oak Ridge National Laboratory's (ORNL) Sustainable Transportation Program research and development efforts are resulting in...

  7. 2012 Annual Report Research Reactor Infrastructure Program

    SciTech Connect (OSTI)

    Douglas Morrell

    2012-11-01T23:59:59.000Z

    The content of this report is the 2012 Annual Report for the Research Reactor Infrastructure Program.

  8. ARS Energy Water and Sustainability Program

    Broader source: Energy.gov [DOE]

    Presentation covers the ARS Energy Water and Sustainability Program given at the Spring 2010 Federal Utility Partnership Working Group (FUPWG) meeting in Rapid City, South Dakota.

  9. University Reactor Matching Grants Program

    SciTech Connect (OSTI)

    John Valentine; Farzad Rahnema; Said Abdel-Khalik

    2003-02-14T23:59:59.000Z

    During the 2002 Fiscal year, funds from the DOE matching grant program, along with matching funds from the industrial sponsors, have been used to support research in the area of thermal-hydraulics. Both experimental and numerical research projects have been performed. Experimental research focused on two areas: (1) Identification of the root cause mechanism for axial offset anomaly in pressurized water reactors under prototypical reactor conditions, and (2) Fluid dynamic aspects of thin liquid film protection schemes for inertial fusion reactor chambers. Numerical research focused on two areas: (1) Multi-fluid modeling of both two-phase and two-component flows for steam conditioning and mist cooling applications, and (2) Modeling of bounded Rayleigh-Taylor instability with interfacial mass transfer and fluid injection through a porous wall simulating the ''wetted wall'' protection scheme in inertial fusion reactor chambers. Details of activities in these areas are given.

  10. Water Sustainability Program Challenges to Sustainable Water

    E-Print Network [OSTI]

    Cushing, Jim. M.

    ¡ Drought, Climate Change ¡ Growth and the need for additional supplies ¡ Water and Energy ¡ Water the Southwest, nation, semi-arid and arid regions, and the world. ¡ Today's program provides just a glimpse to and utilization of renewable supplies ¡ Transboundary water issues ¡ The surface water/groundwater interface

  11. Sustainable Food & Bioenergy Systems Program-Sustainable Crop Production Option 2014-2015 Catalog

    E-Print Network [OSTI]

    Dyer, Bill

    Sustainable Food & Bioenergy Systems Program- Sustainable Crop Production Option 2014-2015 Catalog SFBS 146 Intro to Sustainable Food & Bioenergy Systems ................................ S

  12. WWU Sustainability Committee Subcommittee on Curriculum and Programs

    E-Print Network [OSTI]

    Zaferatos, Nicholas C.

    WWU Sustainability Committee Subcommittee on Curriculum and Programs Sustainability Curriculum Smeins (Art), Nicholas Zaferatos (Huxley College), Seth Vidana (Campus Sustainability Coordinator) Re: Recommendations for establishing a university-wide program in sustainability literacy, experiential learning

  13. Light Water Reactor Sustainability Newsletter Rebecca Smith-Kevern

    Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

    Rebecca Smith-Kevern Director, Office of Light Water Reactor Technologies. I am often asked why the Federal Government should fund a program that supports the continued operation...

  14. The Path to Program Sustainability | Department of Energy

    Office of Energy Efficiency and Renewable Energy (EERE) Indexed Site

    The Path to Program Sustainability The strategies outlined below help create self-sustaining clean energy finance programs. Prove Energy Efficiency Finance as a Profitable...

  15. Stanford University Sustainable Design & Construction Program

    E-Print Network [OSTI]

    Prinz, Friedrich B.

    March 14, 2014 Y2E2 Building, Room 292E 473 Via Ortega, Stanford, CA 94305 #12;Sustainable DesignStanford University Sustainable Design & Construction Program 2014-2015 Admitted Student Open House for sophisticated structural/construction engineers " Support Design-Build Firms, Design Firms, Construction Firms

  16. A Guide to Educational Programs in Environment and Sustainable

    E-Print Network [OSTI]

    Khatiwala, Samar

    1 A Guide to Educational Programs in Environment and Sustainable Development at Columbia;3 A GUIDE TO EDUCATIONAL PROGRAMS IN ENVIROMENT AND SUSTAINABLE DEVELOPMENT AT COLUMBIA UNIVERSITY OFFICE................................................................................................... 6 Areas of study: Sustainable Development

  17. accounting sustainability program: Topics by E-print Network

    Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

    Environment and Sustainable Development at Columbia;3 A GUIDE TO EDUCATIONAL PROGRAMS IN ENVIROMENT AND SUSTAINABLE DEVELOPMENT AT COLUMBIA UNIVERSITY OFFICE......

  18. Programming Guidelines for FBD programs in Reactor Protection

    E-Print Network [OSTI]

    Programming Guidelines for FBD programs in Reactor Protection System Sejin Jung, Dong-Ah Lee, Eui Diagram) to design software ­ It used PLC (Programmable Logic Controller) programming language in plant for the Use of Function Block Diagram in Reactor Protection Systems, accepted APSEC 2014 Research2

  19. Research Program of a Super Fast Reactor

    SciTech Connect (OSTI)

    Oka, Yoshiaki; Ishiwatari, Yuki; Liu, Jie; Terai, Takayuki; Nagasaki, Shinya; Muroya, Yusa; Abe, Hiroaki [Nuclear Professional School / Department of Nuclear Engineering and Management, The University of Tokyo, Tokaimura, Naka-gun, Ibaraki, 319-1188 (Japan); Mori, Hideo [Department of Mechanical Engineering, Kyushu University (Japan); Akiba, Masato; Akimoto, Hajime; Okumura, Keisuke; Akasaka, Naoaki [Japan Atomic Energy Agency (Japan); GOTO, Shoji [Tokyo Electric Power Company (Japan)

    2006-07-01T23:59:59.000Z

    Research program of a supercritical-pressure light water cooled fast reactor (Super Fast Reactor) is funded by MEXT (Ministry of Education, Culture, Sports, Science and Technology) in December 2005 as one of the research programs of Japanese NERI (Nuclear Energy Research Initiative). It consists of three programs. (1) development of Super Fast Reactor concept; (2) thermal-hydraulic experiments; (3) material developments. The purpose of the concept development is to pursue the advantage of high power density of fast reactor over thermal reactors to achieve economic competitiveness of fast reactor for its deployment without waiting for exhausting uranium resources. Design goal is not breeding, but maximizing reactor power by using plutonium from spent LWR fuel. MOX will be the fuel of the Super Fast Reactor. Thermal-hydraulic experiments will be conducted with HCFC22 (Hydro chlorofluorocarbons) heat transfer loop of Kyushu University and supercritical water loop at JAEA. Heat transfer data including effect of grid spacers will be taken. The critical flow and condensation of supercritical fluid will be studied. The materials research includes the development and testing of austenitic stainless steel cladding from the experience of PNC1520 for LMFBR. Material for thermal insulation will be tested. SCWR (Supercritical-Water Cooled Reactor) of GIF (Generation-4 International Forum) includes both thermal and fast reactors. The research of the Super Fast Reactor will enhance SCWR research and the data base. The research period will be until March 2010. (authors)

  20. Extractive Industries and Sustainable Development EXECUTIVE TRAINING PROGRAM

    E-Print Network [OSTI]

    Industries and Sustainable Development EXECUTIVE TRAINING PROGRAM Vale Columbia Center UNIVERSITY Center on Globalization and Sustainable Development EARTH INSTITUTE | COLUMBIA UNIVERSITY #12; Extractive Industries and Sustainable Development Executive Training

  1. Office of Sustainability: Summer 2012 Student Internships Program

    E-Print Network [OSTI]

    Sheridan, Jennifer

    Office of Sustainability: Summer 2012 Student Internships Program University of Wisconsin-Madison 15 April 2012 www.sustainability.wisc.edu The Office of Sustainability (OS) student internships program is intended to engage student creativity, energy, and leadership around sustainability principles

  2. HANFORD SITE SUSTAINABILITY PROGRAM RICHLAND WASHINGTON - 12464

    SciTech Connect (OSTI)

    FRITZ LL

    2012-01-12T23:59:59.000Z

    In support of implementation of Executive Order (EO) 13514, Federal Leadership in Environmental, Energy and Economic Performance, the Hanford Site Sustainability Plan was developed to implement strategies and activities required to achieve the prescribed goals in the EO as well as demonstrate measurable progress in environmental stewardship at the Hanford Site. The Hanford Site Sustainability Program was developed to demonstrate progress towards sustainability goals as defined and established in Executive Order (EO) 13514, Federal Leadership in Environmental, Energy and Economic Performance; EO 13423, Strengthening Federal Environmental, Energy and Transportation Management, and several applicable Energy Acts. Multiple initiatives were undertaken in Fiscal Year (FY) 2011 to implement the Program and poise the Hanford Site as a leader in environmental stewardship. In order to implement the Hanford Site Sustainability Program, a Sustainability Plan was developed in conjunction with prime contractors, two U.S. Department of Energy (DOE) Offices, and key stakeholders to serve as the framework for measuring progress towards sustainability goals. Based on the review of these metrics and future plans, several activities were initiated to proactively improve performance or provide alternatives for future consideration contingent on available funding. A review of the key metric associated with energy consumption for the Hanford Site in FY 2010 and 2011 indicated an increase over the target reduction of 3 percent annually from a baseline established in FY 2003 as illustrated in Figure 1. This slight increase was attributed primarily from the increased energy demand from the cleanup projects funded by the American Recovery and Reinvestment Act (ARRA) in FY 2010 and 2011. Although it is forecasted that the energy demand will decrease commensurate with the completion of ARRA projects, several major initiatives were launched to improve energy efficiency.

  3. The advanced test reactor strategic evaluation program

    SciTech Connect (OSTI)

    Buescher, B.J.; Majumdar, D.; Croucher, D.W.

    1989-01-01T23:59:59.000Z

    Since the Chernobly accident, the safety of test reactors and irradiation facilities has been critically evaluated from the public's point of view. A systematic evaluation of all safety, environmental, and operational issues must be made in an integrated manner to prioritize actions to maximize benefits while minimizing costs. Such a proactive program has been initiated at the Advanced Test Reactor (ATR). This program, called the Strategic Evaluation Program (STEP), is being conducted for the ATR to provide integrated safety and operational reviews of the reactor against the standards applied to licensed commercial power reactors. This has taken into consideration the lessons learned by the US Nuclear Regulatory Commission (NRC) in its Systematic Evaluation Program (SEP) and the follow-on effort known as the Integrated Safety Assessment Program (ISAP). The SEP was initiated by the NRC to review the designs of older operating nuclear power plants to confirm and document their safety. The ATR STEP objectives are discussed.

  4. Robustness of RISMC Insights under Alternative Aleatory/Epistemic Uncertainty Classifications: Draft Report under the Risk-Informed Safety Margin Characterization (RISMC) Pathway of the DOE Light Water Reactor Sustainability Program

    SciTech Connect (OSTI)

    Unwin, Stephen D.; Eslinger, Paul W.; Johnson, Kenneth I.

    2012-09-20T23:59:59.000Z

    The Risk-Informed Safety Margin Characterization (RISMC) pathway is a set of activities defined under the U.S. Department of Energy (DOE) Light Water Reactor Sustainability Program. The overarching objective of RISMC is to support plant life-extension decision-making by providing a state-of-knowledge characterization of safety margins in key systems, structures, and components (SSCs). A technical challenge at the core of this effort is to establish the conceptual and technical feasibility of analyzing safety margin in a risk-informed way, which, unlike conventionally defined deterministic margin analysis, would be founded on probabilistic characterizations of uncertainty in SSC performance. In the context of probabilistic risk assessment (PRA) technology, there has arisen a general consensus about the distinctive roles of two types of uncertainty: aleatory and epistemic, where the former represents irreducible, random variability inherent in a system, whereas the latter represents a state of knowledge uncertainty on the part of the analyst about the system which is, in principle, reducible through further research. While there is often some ambiguity about how any one contributing uncertainty in an analysis should be classified, there has nevertheless emerged a broad consensus on the meanings of these uncertainty types in the PRA setting. However, while RISMC methodology shares some features with conventional PRA, it will nevertheless be a distinctive methodology set. Therefore, the paradigms for classification of uncertainty in the PRA setting may not fully port to the RISMC environment. Yet the notion of risk-informed margin is based on the characterization of uncertainty, and it is therefore critical to establish a common understanding of uncertainty in the RISMC setting.

  5. Light Water Reactor Sustainability Constellation Pilot Project FY13 Summary Report

    SciTech Connect (OSTI)

    R. Johansen

    2013-09-01T23:59:59.000Z

    Summary report for Light Water Reactor Sustainability (LWRS) activities related to the R. E. Ginna and Nine Mile Point Unit 1 for FY13.

  6. Light Water Reactor Sustainability Constellation Pilot Project FY12 Summary Report

    SciTech Connect (OSTI)

    R. Johansen

    2012-09-01T23:59:59.000Z

    Summary report for Light Water Reactor Sustainability (LWRS) activities related to the R. E. Ginna and Nine Mile Point Unit 1 for FY12.

  7. Sustainable Energy Utility- Residential Energy Efficiency Program (District of Columbia)

    Broader source: Energy.gov [DOE]

    The District of Columbia Sustainable Energy Utility currently offers the Residential Energy Efficiency Program. The program provides financial incentives to District residents who install energy-...

  8. N Reactor Deactivation Program Plan. Revision 4

    SciTech Connect (OSTI)

    Walsh, J.L.

    1993-12-01T23:59:59.000Z

    This N Reactor Deactivation Program Plan is structured to provide the basic methodology required to place N Reactor and supporting facilities {center_dot} in a radiologically and environmentally safe condition such that they can be decommissioned at a later date. Deactivation will be in accordance with facility transfer criteria specified in Department of Energy (DOE) and Westinghouse Hanford Company (WHC) guidance. Transition activities primarily involve shutdown and isolation of operational systems and buildings, radiological/hazardous waste cleanup, N Fuel Basin stabilization and environmental stabilization of the facilities. The N Reactor Deactivation Program covers the period FY 1992 through FY 1997. The directive to cease N Reactor preservation and prepare for decommissioning was issued by DOE to WHC on September 20, 1991. The work year and budget data supporting the Work Breakdown Structure in this document are found in the Activity Data Sheets (ADS) and the Environmental Restoration Program Baseline, that are prepared annually.

  9. CSU SCHOOL OF GLOBAL ENVIRONMENTAL SUSTAINABILITY Summer Internship 2014 Pre-College Summer Sustainability Program

    E-Print Network [OSTI]

    CSU SCHOOL OF GLOBAL ENVIRONMENTAL SUSTAINABILITY Summer Internship 2014 Pre-College Summer Sustainability Program 3 Positions Available One (1) Lead Mentor- Available for June 24-July 1 Session AND July 8 The Pre-College Summer Sustainability Program is looking for CSU student Mentors. If you are interested

  10. UCLA program in reactor studies: The ARIES tokamak reactor study

    SciTech Connect (OSTI)

    Not Available

    1991-01-01T23:59:59.000Z

    The ARIES research program is a multi-institutional effort to develop several visions of tokamak reactors with enhanced economic, safety, and environmental features. The aims are to determine the potential economics, safety, and environmental features of a range of possible tokamak reactors, and to identify physics and technology areas with the highest leverage for achieving the best tokamak reactor. Four ARIES visions are currently planned for the ARIES program. The ARIES-1 design is a DT-burning reactor based on modest'' extrapolations from the present tokamak physics database and relies on either existing technology or technology for which trends are already in place, often in programs outside fusion. ARIES-2 and ARIES-4 are DT-burning reactors which will employ potential advances in physics. The ARIES-2 and ARIES-4 designs employ the same plasma core but have two distinct fusion power core designs; ARIES-2 utilize the lithium as the coolant and breeder and vanadium alloys as the structural material while ARIES-4 utilizes helium is the coolant, solid tritium breeders, and SiC composite as the structural material. Lastly, the ARIES-3 is a conceptual D-{sup 3}He reactor. During the period Dec. 1, 1990 to Nov. 31, 1991, most of the ARIES activity has been directed toward completing the technical work for the ARIES-3 design and documenting the results and findings. We have also completed the documentation for the ARIES-1 design and presented the results in various meetings and conferences. During the last quarter, we have initiated the scoping phase for ARIES-2 and ARIES-4 designs.

  11. Advanced Reactors Transition Program Resource Loaded Schedule

    SciTech Connect (OSTI)

    BOWEN, W.W.

    1999-11-08T23:59:59.000Z

    The Advanced Reactors Transition (ART) Resource Loaded Schedule (RLS) provides a cost and schedule baseline for managing the project elements within the ART Program. The Fast Flux Test Facility (FFTF) activities are delineated through the end of FY 2000, assuming continued standby. The Nuclear Energy (NE) Legacies and Plutonium Recycle Test Reactor (PRTR) activities are delineated through the end of the deactivation process. This document reflects the 1 Oct 1999 baseline.

  12. NextSTEPS (Sustainable Transportation Energy Pathways) PROGRAM SUMMARY

    E-Print Network [OSTI]

    California at Davis, University of

    NextSTEPS (Sustainable Transportation Energy Pathways) PROGRAM SUMMARY Institute of Transportation in January 2011, building on the many advances of our Sustainable Transportation Energy Pathways (STEPS Studies University of California, Davis Automakers, energy companies, utilities and governments are making

  13. Comparison of two different rating programs for sustainable homes

    E-Print Network [OSTI]

    Bjarnadottir, Margret Halla

    2009-01-01T23:59:59.000Z

    This thesis compares two different rating programs for sustainable homes; The Code for Sustainable Homes in the United Kingdom, and LEED for Homes in the United States. The comparison is both in general and with respect ...

  14. Light Water Reactor Sustainability Program BWR High-Fluence Material Project: Assessment of the Role of High-Fluence on the Efficiency of HWC Mitigation on SCC Crack Growth Rates

    SciTech Connect (OSTI)

    Sebastien Teysseyre

    2014-04-01T23:59:59.000Z

    As nuclear power plants age, the increasing neutron fluence experienced by stainless steels components affects the materials resistance to stress corrosion cracking and fracture toughness. The purpose of this report is to identify any new issues that are expected to rise as boiling water reactor power plants reach the end of their initial life and to propose a path forward to study such issues. It has been identified that the efficiency of hydrogen water chemistry mitigation technology may decrease as fluence increases for high-stress intensity factors. This report summarizes the data available to support this hypothesis and describes a program plan to determine the efficiency of hydrogen water chemistry as a function of the stress intensity factor applied and fluence. This program plan includes acquisition of irradiated materials, generation of material via irradiation in a test reactor, and description of the test plan. This plan offers three approaches, each with an estimated timetable and budget.

  15. Sustained Recycle in Light Water and Sodium-Cooled Reactors

    SciTech Connect (OSTI)

    Steven J. Piet; Samuel E. Bays; Michael A. Pope; Gilles J. Youinou

    2010-11-01T23:59:59.000Z

    From a physics standpoint, it is feasible to sustain recycle of used fuel in either thermal or fast reactors. This paper examines multi-recycle potential performance by considering three recycling approaches and calculating several fuel cycle parameters, including heat, gamma, and neutron emission of fresh fuel; radiotoxicity of waste; and uranium utilization. The first recycle approach is homogeneous mixed oxide (MOX) fuel assemblies in a light water reactor (LWR). The transuranic portion of the MOX was varied among Pu, NpPu, NpPuAm, or all-TRU. (All-TRU means all isotopes through Cf-252.) The Pu case was allowed to go to 10% Pu in fresh fuel, but when the minor actinides were included, the transuranic enrichment was kept below 8% to satisfy the expected void reactivity constraint. The uranium portion of the MOX was enriched uranium. That enrichment was increased (to as much as 6.5%) to keep the fuel critical for a typical LWR irradiation. The second approach uses heterogeneous inert matrix fuel (IMF) assemblies in an LWR - a mix of IMF and traditional UOX pins. The uranium-free IMF fuel pins were Pu, NpPu, NpPuAm, or all-TRU. The UOX pins were limited to 4.95% U-235 enrichment. The number of IMF pins was set so that the amount of TRU in discharged fuel from recycle N (from both IMF and UOX pins) was made into the new IMF pins for recycle N+1. Up to 60 of the 264 pins in a fuel assembly were IMF. The assembly-average TRU content was 1-6%. The third approach uses fast reactor oxide fuel in a sodium-cooled fast reactor with transuranic conversion ratio of 0.50 and 1.00. The transuranic conversion ratio is the production of transuranics divided by destruction of transuranics. The FR at CR=0.50 is similar to the CR for the MOX case. The fast reactor cases had a transuranic content of 33-38%, higher than IMF or MOX.

  16. Taiwan International Graduate Program Sustainable Chemical Science and Technology

    E-Print Network [OSTI]

    to sustainable energy 2. construction of supramolecular materials for recognition, self- assemblyTaiwan International Graduate Program Sustainable Chemical Science and Technology Taiwan of the Program to offer Ph.D. education programs only in inter-disciplinary areas in the physical sciences

  17. Lincoln Electric System (Commercial and Industrial)- Sustainable Energy Program

    Broader source: Energy.gov [DOE]

    Lincoln Electric System (LES) offers a variety of energy efficiency incentives for commercial and industrial customers through the Sustainable Energy Program (SEP). Some incentives are provided on...

  18. Structuring Rebate and Incentive Programs for Sustainable Demand...

    Broader source: Energy.gov (indexed) [DOE]

    Peer Exchange Call: Structuring Rebate and Incentive Programs for Sustainable Demand, call slides and discussion summary, August 18, 2011. Call Slides and Discussion Summary More...

  19. Chelan County PUD- Sustainable Natural Alternative Power Producers Program

    Broader source: Energy.gov [DOE]

    The Sustainable Natural Alternative Power (SNAP) program encourages customers to install alternative power generators such as solar panels and wind turbines and connect them to the District's...

  20. Reactor Pressure Vessel Task of Light Water Reactor Sustainability Program:

    Broader source: Energy.gov (indexed) [DOE]

    AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE:1 First Use of Energy for All Purposes (Fuel and Nonfuel),Feet) Year Jan Feb Mar Apr May Jun Jul(Summary) "ofEarlyEnergy 0611__Joint_DOE_GoJ_AMS_Data_v3.pptx More DocumentsCommunicationsProvides an overview of

  1. Reactor Pressure Vessel Task of Light Water Reactor Sustainability Program:

    Broader source: Energy.gov (indexed) [DOE]

    AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE:1 First Use of Energy for All Purposes (Fuel and Nonfuel),Feet) Year Jan Feb Mar Apr May Jun Jul(Summary) "ofEarlyEnergy 0611__Joint_DOE_GoJ_AMS_Data_v3.pptx More DocumentsCommunicationsProvides an overview

  2. Reactor Pressure Vessel Task of Light Water Reactor Sustainability Program:

    Broader source: Energy.gov (indexed) [DOE]

    AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE:1 First Use of Energy for All Purposes (Fuel and Nonfuel),Feet) Year Jan Feb Mar Apr May Jun Jul(Summary) "ofEarlyEnergy 0611__Joint_DOE_GoJ_AMS_Data_v3.pptx More DocumentsCommunicationsProvides an overviewMilestone

  3. Unconventional digital reactor control without conventional programming

    SciTech Connect (OSTI)

    Edwards, R.M.; Johns, R.M.; Kenney, S.J. [Pennsylvania State Univ., University Park, PA (United States)

    1995-12-31T23:59:59.000Z

    Recent advances in simulation technology have resulted in the capability to design, test, and implement advanced control algorithms without the need for the labor-intensive effort of writing and debugging of computer programs. This technology has been adopted for a program of experimental development of power reactor control, which is jointly sponsored by the National Science Foundation and the Electric Power Research Institute. The experimental reactor control test bed utilizes the General Atomic Mark III TRIGA reactor at the Penn State Breazeale reactor facility. Control experiments are conducted within the movable experiment technical specifications of the TRIGA. A digital controller with an experimental control algorithm is interfaced to a secondary control rod (SCR). The new technology presented in this paper utilizes a UNIX network-compatible microprocessor-based controller operating under the Wind River Systems VxWorks real-time operating system. The controller interfaces with the Math-works MATLAB/SIMULINK development environment and Real-Time Innovations 8 monitoring software remotely operated on a SPARC workstation.

  4. Sustainable Development Fund Financing Program (PECO Territory)

    Broader source: Energy.gov [DOE]

    The Pennsylvania Public Utility Commission created the Sustainable Development Fund (SDF) in its final order of the PECO Energy electric utility restructuring proceeding. The Reinvestment Fund,...

  5. Reactor Sharing Program. Final report, 1991--1992

    SciTech Connect (OSTI)

    Vernetson, W.G.

    1993-01-01T23:59:59.000Z

    Progress achieved at the University of Florida Training Reactor (UFTR) facility through the US Department of Energy`s University Reactor Sharing Program is reported for the period of 1991--1992.

  6. A guide to sustainability initiatives and programs at Berea College

    E-Print Network [OSTI]

    Baltisberger, Jay H.

    by the Ecological Sustainability Education (ESE) Program Being green is ESE ("easy")! #12;Table of Contents .................................................................................. 13 SENS House ...................................................................................... 19 #12;1 INTRODUCTION With the ecological renovation of several campus buildings, the creation

  7. Los Alamos National Lab staff benchmark Y-12 sustainability programs...

    Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

    Los Alamos National Lab ... Los Alamos National Lab staff benchmark Y-12 sustainability programs Posted: June 27, 2013 - 3:53pm OAK RIDGE, Tenn. - Staff from Los Alamos National...

  8. Sustainable Transportation Program | Clean Energy | ORNL

    Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

    AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE:1 First Use of Energy for All Purposes (Fuel and Nonfuel),Feet) Year Jan Feb Mar Apr MayAtmosphericNuclear Security AdministrationcontrollerNanocrystalline GalliumSuppressionSustainable Success Sustainable

  9. Sustainable Transportation Program | ornl.gov

    Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

    AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE:1 First Use of Energy for All Purposes (Fuel and Nonfuel),Feet) Year Jan Feb Mar Apr MayAtmosphericNuclear Security AdministrationcontrollerNanocrystalline GalliumSuppressionSustainable Success SustainableBrochure

  10. US fast reactor materials and structures program

    SciTech Connect (OSTI)

    Harms, W.O.; Purdy, C.M.

    1984-01-01T23:59:59.000Z

    Materials and structures problems are central to many critical issues concerning the economic competitiveness, reliable performance, and safety of liquid metal fast breeder reactor (LMFBR) power plants. The US Department of Energy has sponsored for many years a national LMFBR materials and structures program. The objectives of the program are (1) to provide the technological basis for assuring that LMFBR components and systems will be free from significant structural failures during their design lifetimes and (2) to develop materials, design methods and criteria, materials property data, and procedures - all aimed at providing for broad flexibility in LMFBR component and system design and operation. Technology areas included in the program are high-temperature structural design; seismic design; mechanical properties design data; fabrication; tribology (friction, wear, and self-welding); coolant technology (sodium and steam/water); advanced structural alloys; and nondestructive testing. It is the purpose of this study to indicate briefly for each of the program's technology areas the objective, the scope, and some significant accomplishments. Future directions for the program are also discussed.

  11. Light Water Reactor Sustainability Program: Integrated Program Plan |

    Energy Savers [EERE]

    AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative Fuels Data Center Home Page on Google Bookmark EERE: Alternative Fuels Data Center Home Page on Office of Inspector General Office0-72.pdfGeorgeDoesn't Happen toLeveraging National LaboratoriesResearch

  12. Light Water Reactor Sustainability Program - Integrated Program Plan |

    Energy Savers [EERE]

    AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative Fuels Data Center Home Page on Google Bookmark EERE: Alternative Fuels Data Center Home Page on Delicious RankCombustion |EnergyonSupport0.pdf5 OPAM SEMIANNUAL REPORT TOJaredKansas1 -

  13. DOE reactor-pumped laser program

    SciTech Connect (OSTI)

    Felty, J.R. [USDOE, Germantown, MD (United States). Defense Programs; Lipinski, R.J.; McArthur, D.A.; Pickard, P.S. [Sandia National Labs., Albuquerque, NM (United States)

    1993-12-31T23:59:59.000Z

    FALCON is a high-power, steady-state, nuclear reactor-pumped laser (RPL) concept that is being developed by the Department of Energy. The FALCON program has experimentally demonstrated reactor-pumped lasing in various mixtures of xenon, argon, neon, and helium at at wavelengths of 585, 703, 725, 1271, 1733, 1792, 2032, 2630, 2650, and 3370 nm with intrinsic efficiency as high as 2.5%. The major strengths of a reactor-pumped laser are continuous high-power operation, modular construction, self-contained power, compact size, and a variety of wavelengths (from visible to infrared). These characteristics suggest numerous applications not easily accessible to other laser types. A ground-based RPL could beam its power to space for such activities as illuminating geosynchronous communication satellites in the earth`s shadow to extend their lives, beaming power to orbital transfer vehicles, removing space debris, and providing power (from earth) to a lunar base during the long lunar night. The compact size and self-contained power also makes an RPL very suitable for ship basing so that power-beaming activities could be situated around the globe. The continuous high power of an RPL opens many potential manufacturing applications such as deep-penetration welding and cutting of thick structures, wide-area hardening of metal surfaces by heat treatment or cladding application, wide-area vapor deposition of ceramics onto metal surfaces, production of sub-micron sized particles for manufacturing of ceramics, wide-area deposition of diamond-like coatings, and 3-D ceramic lithography.

  14. Sustainable Transportation Program 2011 Annual Report

    SciTech Connect (OSTI)

    Vaughan, Kathi H [ORNL

    2012-06-01T23:59:59.000Z

    Highlights of selected research and development efforts at Oak Ridge National Laboratory funded by the Vehicle Technologies Program, Biomass Program, and Hydrogen and Fuel Cells Program of the Department of Energy, Office of Energy Efficiency and Renewable Energy; and the Department of Transportation.

  15. LWRS Program

    Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

    What's New Archive Light Water Reactor Sustainability Program Accomplishments Report: 2013 An accomplishments report highlighting progress in the development of the scientific...

  16. Lincoln Electric System (Residential)- Sustainable Energy Program

    Broader source: Energy.gov [DOE]

    Lincoln Electric System (LES) offers several rebates to residential customers who are interested in upgrading to energy efficient household equipment. The program includes rebates for insulation...

  17. WSRC Reactor Tank Inspection Program (RTIP) status report

    SciTech Connect (OSTI)

    Loibl, M.W.

    1992-01-01T23:59:59.000Z

    Westinghouse Savannah River Company (WSRC) recently completed the initial phase of nondestructive inspections of the Savannah River Site's (SRS) reactor tanks. This program required almost three years to be conceptualized, fabricated, and tested. An additional 20 months were required to complete the NDE inspection of the P, K and L reactor tanks. The overall cost of the program to date is approximately $25 MM. This status report will address: (1) A brief review of the RTIP program and the constraints which had to be overcome (2) A summary of the examination results of the P,K, and L Reactor tanks. (3) A projection of the future enhancements and capabilities presently in development.

  18. Successful Implementation of a Sustainable Trap Management Program.

    E-Print Network [OSTI]

    Walter, J.

    2013-01-01T23:59:59.000Z

    significant cost penalty in delaying implementation of a program to manage the steam trap population. Plants typically embark on a trap management initiative by focusing on a survey, but may not maximize returns because they fail to execute or sustain possible...

  19. Sustainability

    Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

    INL Logo Search Sustainability Home About Sustainable INL Electronics Stewardship Energy Efficiency Fleet Management Green Purchasing Recycling Renewable Energy Sustainable...

  20. Reactor safety research programs. Quarterly report Apr-Jun 81

    SciTech Connect (OSTI)

    Edler, S.K.

    1981-09-01T23:59:59.000Z

    This document summarizes the work performed by Pacific Northwest Laboratory (PNL) from April 1 through June 30, 1981, for the Division of Reactor Safety Research within the U.S. Nuclear Regulatory Commission (NRC). Evaluations of nondestructive examination (NDE) techniques and instrumentation are reported; areas of investigation include demonstrating the feasibility of determining the strength of structural graphite, evaluating the feasibility of detecting and analyzing flaw growth in reactor pressure boundary systems, examining NDE reliability and probabilistic fracture mechanics, and assessing the integrity of pressurized water reactor (PWR) steam generator tubes where service-induced degradation has been indicated. Experimental data and analytical models are being provided to aid in decision-making regarding pipe-to-pipe impacts following postulated breaks in high-energy fluid system piping. Core thermal models are being developed to provide better digital codes to compute the behavior of full-scale reactor systems under postulated accident conditions. Fuel assemblies and analytical support are being provided for experimental programs at other facilities. These programs include loss-of-coolant accident (LOCA) simulation tests at the NRU reactor, Chalk River, Canada; fuel rod deformation, severe fuel damage, and postaccident coolability tests for the ESSOR reactor Super Sara Test Program, Ispra, Italy; the instrumented fuel assembly irradiation program at Halden, Norway; and experimental programs at the Power Burst Facility, Idaho National Engineering Laboratory (INEL). These programs will provide data for computer modeling of reactor system and fuel performance during various abnormal operating conditions.

  1. Reactor Safety Research Programs Quarterly Report April- June 1981

    SciTech Connect (OSTI)

    Edler, S. K.

    1981-09-01T23:59:59.000Z

    This document summarizes the work performed by Pacific Northwest laboratory (PNL} from April1 through June 30, 1981, for the Division of Reactor Safety Research within the U.S. Nuclear Regulatory Commission (NRC). Evaluations of nondestructive examination (NDE) techniques and instrumentation are reported; areas of investigation include demonstrating the feasibility of determining the strength of structural graphite, evaluating the feasibility of detecting and analyzing flaw growth in reactor pressure boundary systems, examining NDE reliability and probabilistic fracture mechanics, and assessing the integrity of pressurized water reactor (PWR) steam generator tubes where service-induced degradation has been indicated. Experimental data and analytical models are being provided to aid in decision-making regarding pipe-to-pipe impacts following postulated breaks in high-energy fluid system piping. Core thermal models are being developed to provide better digital codes to compute the behavior of full-scale reactor systems under postulated accident conditions. Fuel assemblies and analytical support are being provided for experimental programs at other facilities. These programs include loss-of-coolant accident (LOCA) simulation tests at the NRU reactor, Chalk River, Canada; fuel rod deformation, severe fuel damage, and postaccident coolability tests for the ESSOR reactor Super Sara Test Program, lspra, Italy; the instrumented fuel assembly irradiation program at Halden, Norway; and experimental programs at the Power Burst Facility, Idaho National Engineering Laboratory {INEL). These programs will provide data for computer modeling of reactor system and fuel performance during various abnormal operating conditions.

  2. Reactor Safety Research Programs Quarterly Report January - March 1980

    SciTech Connect (OSTI)

    Hagen, C. M

    1980-10-01T23:59:59.000Z

    This document summarizes the work performed by Pacific Northwest Laboratory from January 1 through March 31, 1980, for the Division of Reactor Safety Research within the Nuclear Regulatory Commission. Evaluation of nondestructive examination (NDE) techniques and instrumentation are reported; areas of investigation include demonstrating the feasibilty of determining structural graphite strength, evaluating the feasibilty of detecting and analyzing flaw growth in reactor pressure boundary systems, examining NDE reliability and probabilistic fracture mechanics, and assessing the remaining integrity of pressurized water reactor steam generator tubes where serviceinduced degradation has been indicated. Test assemblies and analytical support are being provided for experimental programs at other facilities. These programs include the loss-of-coolant accident simulation tests at the NRU reactor, Chalk River, Canada; the fuel rod deformation and post-accident coolability tests for the ESSOR Test Reactor Program, Ispra, Italy; the blowdown and reflood tests in the test facility at Cadarache, France; the instrumented fuel assembly irradiation program at Halden, Norway; and the experimental programs at the Power Burst Facility, Idaho National Engineering Laboratory. These programs will provide data for computer modeling of reactor system and fuel performance during various abnormal operating conditions.

  3. Reactor Safety Research Programs Quarterly Report July- September 1980

    SciTech Connect (OSTI)

    Edler, S. K.

    1980-12-01T23:59:59.000Z

    This document summarizes the work performed by Pacific Northwest Laboratory (PNL) from April 1 through June 30, 1980, for the Division of Reactor Safety Research within the Nuclear Regulatory Commission {NRC). Evaluations of nondestructive examination (NDE) techniques and instrumentation are reported; areas of investigation include demonstrating the feasibility of determining structural graphite strength, evaluating the feasibility of detecting and analyzing flaw growth in reactor pressure boundary systems, examining NDE reliability and probabilistic fracture mechanics, and assessing the remaining integrity of pressurized water reactor (PWR) steam generator tubes where service-induced degradation has been indicated. Test assemblies and analytical support are being provided for experimental programs at other facilities. These programs include loss-of-coolant accident (LOCA) simulation tests at the NRU reactor, Chalk River, Canada; fuel rod deformation and postaccident coolability tests for the ESSOR Test Reactor Program, Ispra, Italy; blowdown and reflood tests in the test facility at Cadarache, France; the instrumented fuel assembly irradiation program at Halden, Norway; and experimental programs at the Power Burst Facility, Idaho National Engineering Laboratory (INEL). These programs will provide data for computer modeling of reactor system and fuel performance during various abnormal operating conditions.

  4. Reactor Safety Research Programs Quarterly Report April -June 1980

    SciTech Connect (OSTI)

    Edler, S. K.

    1980-11-01T23:59:59.000Z

    This document summarizes the work performed by Pacific Northwest Laboratory (PNL) from April 1 through June 30, 1980, for the Division of Reactor Safety Research within the Nuclear Regulatory Commission {NRC). Evaluations of nondestructive examination (NDE) techniques and instrumentation are reported; areas of investigation include demonstrating the feasibility of determining structural graphite strength, evaluating the feasibility of detecting and analyzing flaw growth in reactor pressure boundary systems, examining NDE reliability and probabilistic fracture mechanics, and assessing the remaining integrity of pressurized water reactor (PWR) steam generator tubes where service-induced degradation has been indicated. Test assemblies and analytical support are being provided for experimental programs at other facilities. These programs include loss-of-coolant accident (LOCA) simulation tests at the NRU reactor, Chalk River, Canada; fuel rod deformation and postaccident coolability tests for the ESSOR Test Reactor Program, Ispra, Italy; blowdown and reflood tests in the test facility at Cadarache, France; the instrumented fuel assembly irradiation program at Halden, Norway; and experimental programs at the Power Burst Facility, Idaho National Engineering Laboratory (INEL). These programs will provide data for computer modeling of reactor system and fuel performance during various abnormal operating conditions.

  5. Reactor Safety Research Programs Quarterly Report July - September 1981

    SciTech Connect (OSTI)

    Edler, S. K.

    1982-01-01T23:59:59.000Z

    This document summarizes the work performed by Pacific Northwest laboratory (PNL) from July 1 through September 30, 1981, for the Division of Accident Evaluation, U.S. Nuclear Regulatory Commission (NRC). Evaluations of nondestructive examination (NDE) techniques and instrumentation are reported; areas of investigation include demonstrating the feasibility of determining the strength of structural graphite, evaluating the feasibility of detecting and analyzing flaw growth in reactor pressure boundary systems, examining NDE reliability and probabilistic fracture mechanics, and assessing the integrity of pressurized water reactor (PWR} steam generator tubes where service-induced degradation has been indicated. Experimental data and analytical models are being provided to aid in decision-making regarding pipe-to-pipe impacts following postulated breaks in high-energy fluid system piping. Core thermal models are being developed to provide better digital codes to compute the behavior of full-scale reactor systems under postulated accident conditions. Fuel assemblies and analytical support are being provided for experimental programs at other facilities. These programs include loss-of-coolant accident (LOCA) simulation tests at the NRU reactor, Chalk River, Canada; fuel rod deformation, severe fuel damage, and postaccident coolability tests for the ESSOR reactor Super Sara Test Program, lspra, Italy; the instrumented fuel assembly irradiation program at Halden, Norway; and experimental programs at the Power Burst Facility, Idaho National Engineering Laboratory (INEL), Idaho Falls, Idaho. These programs will provide data for computer modeling of reactor system and fuel performance during various abnormal operating conditions.

  6. Reactor Safety Research Programs Quarterly Report October - December 1980

    SciTech Connect (OSTI)

    Edler, S K

    1981-04-01T23:59:59.000Z

    This document summarizes the work performed by Pacific Northwest Laboratory (PNL) from October 1 through December 31, 1980, for the Division of Reactor Safety Research within the U.S. Nuclear Regulatory Commission (NRC). Evaluations of nondestructive examination (NDE) techniques and instrumentation are reported; areas of investigation include demonstrating the feasibility of determining structural graphite strength, evaluating the feasibility of detecting and analyzing flaw growth in reactor pressure boundary systems, examining NOE reliability and probabilistic fracture mechanics, and assessing the remaining integrity of pressurized water reactor (PWR) steam generator tubes where service-induced degradation has been indicated. Test assemblies and analytical support are being provided for experimental programs at other facilities. These programs include loss-of-coolant accident (LOCA) simulation tests at the NRU reactor, Chalk River, Canada; fuel rod deformation and postaccident coolability tests for the ESSOR Test Reactor Program, Ispra, Italy; the instrumented fuel assembly irradiation program at Halden, Norway; and experimental programs at the Power Burst Facility, Idaho National Engineering Laboratory (INEL). These programs will provide data for computer modeling of reactor system and fuel performance during various abnormal operating conditions.

  7. Reactor Safety Research Programs Quarterly Report October - December 1981

    SciTech Connect (OSTI)

    Edler, S. K.

    1982-03-01T23:59:59.000Z

    This document summarizes the work performed by Pacific Northwest laboratory (PNL) from October 1 through December 31, 1981, for the Division of Accident Evaluation, U.S. Nuclear Regulatory Commission (NRC). Evaluations of nondestructive examination (NDE) techniques and instrumentation are reported; areas of investigation include demonstrating the feasibility of determining the strength of structural graphite, evaluating the feasibility of detecting and analyzing flaw growth in reactor pressure boundary systems, examining NDE reliability and probabilistic fracture mechanics, and assessing the integrity of pressurized water reactor (PWR) steam generator tubes where serviceinduced degradation has been indicated. Experimental data and analytical models are being provided to aid in decision-making regarding pipe-to-pipe impacts following postulated breaks in high-energy fluid system piping. Core thermal models are being developed to provide better digital codes to compute the behavior of full-scale reactor systems under postulated accident conditions. Fuel assemblies and analytical support are being provided for experimental programs at other facilities. These programs include loss-of-coolant accident (LOCA) simulation tests at the NRU reactor, Chalk River, Canada; fuel rod deformation, severe fuel damage, and post accident coolability tests for the ESSOR reactor Super Sara Test Program, lspra, Italy; the instrumented fuel assembly irradiation program at Halden, Norway; and experimental programs at the Power Burst Facility, Idaho National Engineering Laboratory (INEL), Idaho Falls, Idaho. These programs will provide data for computer modeling of reactor system and fuel performance during various abnormal operating conditions.

  8. Establishment of a Hub for the Light Water Reactor Sustainability Online Monitoring Community

    SciTech Connect (OSTI)

    Nancy J. Lybeck; Magdy S. Tawfik; Binh T. Pham

    2011-08-01T23:59:59.000Z

    Implementation of online monitoring and prognostics in existing U.S. nuclear power plants will involve coordinating the efforts of national laboratories, utilities, universities, and private companies. Internet-based collaborative work environments provide necessary communication tools to facilitate interaction between geographically diverse participants. Available technologies were considered, and a collaborative workspace was established at INL as a hub for the light water reactor sustainability online monitoring community.

  9. ACADEMIC SENATE POLICY #S06-238 INDICATORS AND STANDARDS OF GRADUATE PROGRAM QUALITY AND SUSTAINABILITY

    E-Print Network [OSTI]

    AND SUSTAINABILITY An explicit goal of the University's 2005-2010 strategic plan is that the institution "offers high program quality and sustainability"2 and for the integration of those standards into a "revised process to demonstrate whether University-wide and program-specific indicators and standards of program sustainability

  10. Roadmap to a Sustainable Structured Trusted Employee Program

    SciTech Connect (OSTI)

    Coates, Cameron W [ORNL; Eisele, Gerhard R [ORNL

    2013-08-01T23:59:59.000Z

    Organizations (facility, regulatory agency, or country) have a compelling interest in ensuring that individuals who occupy sensitive positions affording access to chemical biological, radiological and nuclear (CBRN) materials facilities and programs are functioning at their highest level of reliability. Human reliability and human performance relate not only to security but also focus on safety. Reliability has a logical and direct relationship to trustworthiness for the organization is placing trust in their employees to conduct themselves in a secure, safe, and dependable manner. This document focuses on providing an organization with a roadmap to implementing a successful and sustainable Structured Trusted Employee Program (STEP).

  11. Safety program considerations for space nuclear reactor systems

    SciTech Connect (OSTI)

    Cropp, L.O.

    1984-08-01T23:59:59.000Z

    This report discusses the necessity for in-depth safety program planning for space nuclear reactor systems. The objectives of the safety program and a proposed task structure is presented for meeting those objectives. A proposed working relationship between the design and independent safety groups is suggested. Examples of safety-related design philosophies are given.

  12. Reduced-Enrichment Research and Test Reactor Program: Environmental assessment

    SciTech Connect (OSTI)

    Not Available

    1980-05-01T23:59:59.000Z

    The principal program objective and principal part of the proposed action is to improve the proliferation resistance of nuclear fuels used in research and test reactors by providing the technical means (through technical development, design, and testing) for reducing the uranium enrichment requirements of these fuels to substantially less than the 90 to 93% enrichment currently used. Operator acceptance of the reduced-enrichment-uranium (REU) fuel alternative will require minimizing of reactor performance reduction, fuel cycle cost increases, the number of new safety and licensing issues raised, and reactor and facility modifications. The other part of the proposed action is to assure the capability for commercial production and supply of REU fuel for use both in the US and abroad. The RERTR Program scope is limited to generic design studies, technical support to reactor operating organizations in preparing for conversions to REU fuels, fuel development, fuel demonstrations, and technical support for commercialization of REU fuels. This environmental assessment addresses the environmental consequences of RERTR Program activities and of specific conversions of typical reactors (the Ford Nuclear Reactor and one or two other to-be-designated demonstrations) to REU-fuel cycles, including domestic and international shipments of enriched uranium pertinent to the conduct of RERTR Program activities.

  13. PPPL3224, Preprint: February 1997, UC420, 426 Plasma Transport Control and SelfSustaining Fusion Reactor*

    E-Print Network [OSTI]

    to demonstrate this concept with D­T reactor­grade plasmas. For edge transport control, a method based an economical and environmentally sound fusion reactor prototype is the ultimate goal of controlled fusionPPPL­3224, Preprint: February 1997, UC­420, 426 Plasma Transport Control and Self­Sustaining Fusion

  14. PPPL-3224, Preprint: February 1997, UC-420, 426 Plasma Transport Control and Self-Sustaining Fusion Reactor*

    E-Print Network [OSTI]

    to demonstrate this concept with D-T reactor-grade plasmas. For edge transport control, a method based an economical and environmentally sound fusion reactor prototype is the ultimate goal of controlled fusionPPPL-3224, Preprint: February 1997, UC-420, 426 Plasma Transport Control and Self-Sustaining Fusion

  15. Role of small lead-cooled fast reactors for international deployment in worldwide sustainable nuclear energy supply.

    SciTech Connect (OSTI)

    Sienicki, J. J.; Wade, D. C.; Moisseytsev, A.; Nuclear Engineering Division

    2008-01-01T23:59:59.000Z

    Most recently, the global nuclear energy partnership (GNEP) has identified, as one of its key objectives, the development and demonstration of concepts for small and medium-sized reactors (SMRs) that can be globally deployed while assuring a high level of proliferation resistance. Lead-cooled systems offer several key advantages in meeting these goals. The small lead-cooled fast reactor concept known as the small secure transportable autonomous reactor (SSTAR) has been under ongoing development as part of the US advanced nuclear energy systems programs. Meeting future worldwide projected energy demands during this century (e.g., 1000 to 2000 GWe by 2050) in a sustainable manner while maintaining CO2 emissions at or below today's level will require massive deployments of nuclear reactors in non-fuel cycle states as well as fuel cycle states. The projected energy demands of non-fuel cycle states will not be met solely through the deployment of Light Water Reactors (LWRs) in those states without using up the world's resources of fissile material (e.g., known plus speculative virgin uranium resources = 15 million tonnes). The present U.S. policy is focused upon domestic deployment of large-scale LWRs and sodium-cooled fast spectrum Advanced Burner Reactors (ABRs) working in a symbiotic relationship that burns existing fissile material while destroying the actinides which are generated. Other major nuclear nations are carrying out the development and deployment of SFR breeders as witness the planning for SFR breeder deployments in France, Japan, China, India, and Russia. Small (less that 300 MWe) and medium (300 to 700 MWe) size reactors are better suited to the growing economies and infrastructures of many non-fuel cycle states and developing nations. For those deployments, fast reactor converters which are fissile self-sufficient by creating as much fissile material as they consume are preferred to breeders that create more fissile material than they consume. Thus, there is a need for small and medium size fast reactors in non-fuel cycle states operating in a converter mode as well as large sodium-cooled fast breeders in fuel cycle states. Desired attributes for exportable small fast reactors include: proliferation resistance features such as restricted access to fuel; long core life further restricting access by reducing or eliminating the need for refueling; restricted potential to be misused in a breeding mode; fuel form that is unattractive in the safeguards sense; and a conversion ratio of unity to self-generate as much fissile material as is consumed. Desired attributes for exportable small reactor deployments in developing nations and remote sites also include: a small power level to match the smaller demand of towns or sites that are off-grid or on immature local grids; low enough cost to be economically competitive with alternative energy sources available to developing nation customers (e.g. diesel generators in remote locations); readily transported and assembled from transportable modules; simple to operate and highly reliable reducing plant operating staff requirements; as well as high reliability and passive safety reducing the number of accident initiators and need for safety systems as well as reducing the size of the exclusion and emergency planning zones. The Lead-Cooled Fast Reactor (LFR) has the desired attributes. An example of a small exportable LFR concept is the 20 MWe (45 MWt) Small Secure Transportable Autonomous Reactor (SSTAR) incorporating proliferation resistance, fissile selfsufficiency, autonomous load following, a high degree of passive safety, and supercritical carbon dioxide Brayton cycle energy conversion for high plant efficiency and improved economic competitiveness.

  16. WSRC Reactor Tank Inspection Program (RTIP) status report

    SciTech Connect (OSTI)

    Loibl, M.W.

    1992-06-01T23:59:59.000Z

    Westinghouse Savannah River Company (WSRC) recently completed the initial phase of nondestructive inspections of the Savannah River Site`s (SRS) reactor tanks. This program required almost three years to be conceptualized, fabricated, and tested. An additional 20 months were required to complete the NDE inspection of the P, K and L reactor tanks. The overall cost of the program to date is approximately $25 MM. This status report will address: (1) A brief review of the RTIP program and the constraints which had to be overcome (2) A summary of the examination results of the P,K, and L Reactor tanks. (3) A projection of the future enhancements and capabilities presently in development.

  17. Integral Fast Reactor Program annual progress report, FY 1991

    SciTech Connect (OSTI)

    Not Available

    1992-06-01T23:59:59.000Z

    This report summarizes highlights of the technical progress made in the Integral Fast Reactor (IFR) Program in FY 1991. Technical accomplishments are presented in the following areas of the IFR technology development activities: (1) metal fuel performance, (2) pyroprocess development, (3) safety experiments and analyses, (4) core design development, (5) fuel cycle demonstration, and (6) LMR technology R&D.

  18. Integral Fast Reactor Program annual progress report, FY 1991

    SciTech Connect (OSTI)

    Not Available

    1992-06-01T23:59:59.000Z

    This report summarizes highlights of the technical progress made in the Integral Fast Reactor (IFR) Program in FY 1991. Technical accomplishments are presented in the following areas of the IFR technology development activities: (1) metal fuel performance, (2) pyroprocess development, (3) safety experiments and analyses, (4) core design development, (5) fuel cycle demonstration, and (6) LMR technology R D.

  19. Integral Fast Reactor Program annual progress report, FY 1994

    SciTech Connect (OSTI)

    Chang, Y.I.; Walters, L.C.; Laidler, J.J.; Pedersen, D.R.; Wade, D.C.; Lineberry, J.J.

    1994-12-01T23:59:59.000Z

    This report summarizes highlights of the technical progress made in the Integral Fast Reactor (IFR) Program in FY 1994. Technical accomplishments are presented in the following areas of the IFR technology development activities: metal fuel performance; pyroprocess development; safety experiments and analyses; core design development; fuel cycle demonstration; and LMR technology R&D.

  20. Integral Fast Reactor Program. Annual progress report, FY 1992

    SciTech Connect (OSTI)

    Chang, Y.I.; Walters, L.C.; Laidler, J.J.; Pedersen, D.R.; Wade, D.C.; Lineberry, M.J.

    1993-06-01T23:59:59.000Z

    This report summarizes highlights of the technical progress made in the Integral Fast Reactor (IFR) Program in FY 1992. Technical accomplishments are presented in the following areas of the IFR technology development activities: (1) metal fuel performance, (2) pyroprocess development, (3) safety experiments and analyses, (4) core design development, (5) fuel cycle demonstration, and (6) LMR technology R&D.

  1. Microsoft Word - Light Water Reactor Sustainability Program Advanced...

    Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

    on operator attention demands and limitations on operator activities based on the current conduct of operations protocols. This report will identify opportunities to maximize...

  2. Light Water Reactor Sustainability Program - Non-Destructive Evaluation

    Energy Savers [EERE]

    AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative Fuels Data Center Home Page on Google Bookmark EERE: Alternative Fuels Data Center Home Page on Office of Inspector General Office0-72.pdfGeorgeDoesn't Happen toLeveraging National LaboratoriesResearch andR&D

  3. Light Water Reactor Sustainability Program: Materials Aging and Degradation

    Energy Savers [EERE]

    AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative Fuels Data Center Home Page on Google Bookmark EERE: Alternative Fuels Data Center Home Page on Office of Inspector General Office0-72.pdfGeorgeDoesn't Happen toLeveraging National LaboratoriesResearchTechnical

  4. Partnering with Utilities and Other Program Administrators to Sustain-Grow Your Energy Efficiency Initiatives

    Broader source: Energy.gov [DOE]

    This document contains the transcript for the Partnering with Utilities and Other Program Administrators to Sustain and Grow Your Energy Efficiency Initiatives webinar held on May 8, 2013.

  5. Status of reduced enrichment program for research reactors in Japan

    SciTech Connect (OSTI)

    Unesaki, Hironobu [Research Reactor Institute, Kyoto University, Asashiro-nishi 2-1010, Kumatori-cho, Sennan-gun, Osaka 590-0494 (Japan); Ohta, Kazunori; Inoue, Takeshi [Japan Atomic Energy Agency, Shirakata Shirane 2-4, Tokai-mura, Naka-gun, Ibaraki-ken 319-1195 (Japan)

    2008-07-15T23:59:59.000Z

    The status of reduced enrichment program for research reactors in Japan will be reviewed. The reduced enrichment programs for the JRR-3M, JRR-4 and JMTR of Japan Atomic Energy Agency (JAEA, former name is Japan Atomic Energy Research Institute (JAERI)) has been completed by 1999, and the reactors are being satisfactory operated using LEU fuels. The KUR of Kyoto University Research Reactor Institute (KURRI) has been partially completed and is still in progress under the Joint Study Program with Argonne National Laboratory (ANL). The JRR-3M using LEU silicide fuel elements have done a functional test by the Japanese Government in 2000, and the property of the reactor core was satisfied. JAEA has established a 'U-Mo fuel ad hoc committee' and has been studying the U-Mo fuel installation plan by carefully observing the development situation of the U-Mo fuel. In KURRI, the KUR has terminated its operation using HEU fuel on February 2006. The HEU KUR spent fuel elements will be sent to the U.S. by March 2008. Licensing for the full core conversion of KUR to LEU fuel is under progress and the core conversion to LEU is expected to be completed in 2008. (author)

  6. Surveillance program for WWER-440/Type 213 reactor pressure vessels -- Standard program, re-evaluation of results, supplementary program

    SciTech Connect (OSTI)

    Brumovsky, M.; Novosad, P.; Zdarek, J. [Nuclear Research Inst. Rez plc (Czech Republic)

    1996-12-31T23:59:59.000Z

    Irradiation embrittlement of the reactor pressure vessel beltline materials of WWER-440/Type 213 reactors is monitored by a material irradiation surveillance program. Due to the high lead factor, the duration of the standard surveillance program is only five years, after which no further surveillance samples remain in the reactor. The large variation and uncertainty in neutron flux over the irradiated materials produce significant scatter in mechanical properties and necessitate a re-evaluation of results using gamma scanning, specimen reconstitution and recalculation. In order to provide information on the impact of changes in plant operation during later years a supplementary surveillance program has been devised.

  7. Reactor safety research programs. Quarterly report, July-September 1983

    SciTech Connect (OSTI)

    Edler, S.K. (ed.)

    1984-04-01T23:59:59.000Z

    Evaluations of nondestructive examination (NDE) techniques and instrumentation include demonstrating the feasibility of determining the strength of structural graphite, evaluating the feasibility of detecting and analyzing flaw growth in reactor pressure boundary systems, and examining NDE reliability and probabilistic fracture mechanics. Accelerated pellet-cladding interaction modeling is being conducted to predict the probability of fuel rod failure under normal operating conditions. Experimental data and analytical models are being provided to aid in decision making regarding pipe-to-pipe impacts following postulated breaks in high-energy fluid system piping. Experimental data and validated models are being used to determine a method for evaluating the acceptance of welded or weld-repaired stainless steel piping. Thermal-hydraulic models are being developed to provide better digital codes to compute the behavior of full-scale reactor systems under postulated accident conditions. High-temperature materials property tests are being conducted to provide data on severe core damage fuel behavior. Severe fuel damage accident tests are being conducted at the NRU reactor, Chalk River, Canada; and an instrumented fuel assembly irradiation program is being performed at Halden, Norway. Fuel assemblies and analytical support are being provided for experimental programs at other facilities, including the Super Sara Test Program, Ispra, Italy, and experimental programs at the Power Burst Facility.

  8. Generation IV Reactors Integrated Materials Technology Program Plan: Focus on Very High Temperature Reactor Materials

    SciTech Connect (OSTI)

    Corwin, William R [ORNL; Burchell, Timothy D [ORNL; Katoh, Yutai [ORNL; McGreevy, Timothy E [ORNL; Nanstad, Randy K [ORNL; Ren, Weiju [ORNL; Snead, Lance Lewis [ORNL; Wilson, Dane F [ORNL

    2008-08-01T23:59:59.000Z

    Since 2002, the Department of Energy's (DOE's) Generation IV Nuclear Energy Systems (Gen IV) Program has addressed the research and development (R&D) necessary to support next-generation nuclear energy systems. The six most promising systems identified for next-generation nuclear energy are described within this roadmap. Two employ a thermal neutron spectrum with coolants and temperatures that enable hydrogen or electricity production with high efficiency (the Supercritical Water Reactor-SCWR and the Very High Temperature Reactor-VHTR). Three employ a fast neutron spectrum to enable more effective management of actinides through recycling of most components in the discharged fuel (the Gas-cooled Fast Reactor-GFR, the Lead-cooled Fast Reactor-LFR, and the Sodium-cooled Fast Reactor-SFR). The Molten Salt Reactor (MSR) employs a circulating liquid fuel mixture that offers considerable flexibility for recycling actinides and may provide an alternative to accelerator-driven systems. At the inception of DOE's Gen IV program, it was decided to significantly pursue five of the six concepts identified in the Gen IV roadmap to determine which of them was most appropriate to meet the needs of future U.S. nuclear power generation. In particular, evaluation of the highly efficient thermal SCWR and VHTR reactors was initiated primarily for energy production, and evaluation of the three fast reactor concepts, SFR, LFR, and GFR, was begun to assess viability for both energy production and their potential contribution to closing the fuel cycle. Within the Gen IV Program itself, only the VHTR class of reactors was selected for continued development. Hence, this document will address the multiple activities under the Gen IV program that contribute to the development of the VHTR. A few major technologies have been recognized by DOE as necessary to enable the deployment of the next generation of advanced nuclear reactors, including the development and qualification of the structural materials needed to ensure their safe and reliable operation. The focus of this document will be the overall range of DOE's structural materials research activities being conducted to support VHTR development. By far, the largest portion of material's R&D supporting VHTR development is that being performed directly as part of the Next-Generation Nuclear Plant (NGNP) Project. Supplementary VHTR materials R&D being performed in the DOE program, including university and international research programs and that being performed under direct contracts with the American Society for Mechanical Engineers (ASME) Boiler and Pressure Vessel Code, will also be described. Specific areas of high-priority materials research that will be needed to deploy the NGNP and provide a basis for subsequent VHTRs are described, including the following: (1) Graphite: (a) Extensive unirradiated materials characterization and assessment of irradiation effects on properties must be performed to qualify new grades of graphite for nuclear service, including thermo-physical and mechanical properties and their changes, statistical variations from billot-to-billot and lot-to-lot, creep, and especially, irradiation creep. (b) Predictive models, as well as codification of the requirements and design methods for graphite core supports, must be developed to provide a basis for licensing. (2) Ceramics: Both fibrous and load-bearing ceramics must be qualified for environmental and radiation service as insulating materials. (3) Ceramic Composites: Carbon-carbon and SiC-SiC composites must be qualified for specialized usage in selected high-temperature components, such as core stabilizers, control rods, and insulating covers and ducting. This will require development of component-specific designs and fabrication processes, materials characterization, assessment of environmental and irradiation effects, and establishment of codes and standards for materials testing and design requirements. (4) Pressure Vessel Steels: (a) Qualification of short-term, high-temperature properties of light water rea

  9. Optimization strategies for sustainable fuel cycle of the BR2 Reactor

    SciTech Connect (OSTI)

    Kalcheva, S.; Van Den Branden, G.; Koonen, E. [SCK-CEN, BR2 Reactor, Boeretang 200, Mol, 2400 (Belgium)

    2013-07-01T23:59:59.000Z

    The objective of the present study is to achieve a sustainable fuel cycle in a long term of reactor operation applying advanced in-core loading strategies. The optimization criteria concern mainly enhancement of nuclear safety by means of reactivity margins and minimization of the operational fuel cycle cost at a given (constant) power level and same or longer cycle length. An important goal is also to maintain the same or to improve the experimental performances. Current developments are focused on optimization of control rods localization; optimization of fresh and burnt fuel assemblies in-core distribution; optimization of azimuth and axial fuel burn up strategies, including fuel assembly rotating and flipping upside down. (authors)

  10. Building for the future The Green Building and Sustainable Design Certificate Program addresses

    E-Print Network [OSTI]

    California at Davis, University of

    Building for the future The Green Building and Sustainable Design Certificate Program addresses for implementation of green building and sustainable design into site planning and design, building design and construction, and building management practices. Started as a joint program between two of UC Davis Extension

  11. Sustainability

    Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

    innovation. For this second report our major targets included: * Energy reduction; * Water reduction; * Fuel efficiency; * Electronic stewardship; * Sustainable acquisition; *...

  12. Report from the Light Water Reactor Sustainability Workshop on Advanced Instrumentation, Information, and Control Systems and Human-System Interface Technologies

    SciTech Connect (OSTI)

    Bruce P. Hallbert; J. J. Persensky; Carol Smidts; Tunc Aldemir; Joseph Naser

    2009-08-01T23:59:59.000Z

    The Light Water Reactor Sustainability (LWRS) Program is a research and development (R&D) program sponsored by the U.S. Department of Energy (DOE). The program is operated in close collaboration with industry R&D programs to provide the technical foundations for licensing and managing the long-term, safe, and economical operation of Nuclear Power Plants that are currently in operation. The LWRS Program focus is on longer-term and higher-risk/reward research that contributes to the national policy objectives of energy and environmental security. Advanced instruments and control (I&C) technologies are needed to support the safe and reliable production of power from nuclear energy systems during sustained periods of operation up to and beyond their expected licensed lifetime. This requires that new capabilities to achieve process control be developed and eventually implemented in existing nuclear assets. It also requires that approaches be developed and proven to achieve sustainability of I&C systems throughout the period of extended operation. The strategic objective of the LWRS Program Advanced Instrumentation, Information, and Control Systems Technology R&D pathway is to establish a technical basis for new technologies needed to achieve safety and reliability of operating nuclear assets and to implement new technologies in nuclear energy systems. This will be achieved by carrying out a program of R&D to develop scientific knowledge in the areas of: • Sensors, diagnostics, and prognostics to support characterization and prediction of the effects of aging and degradation phenomena effects on critical systems, structures, and components (SSCs) • Online monitoring of SSCs and active components, generation of information, and methods to analyze and employ online monitoring information • New methods for visualization, integration, and information use to enhance state awareness and leverage expertise to achieve safer, more readily available electricity generation. As an initial step in accomplishing this effort, the Light Water Reactor Sustainability Workshop on Advanced Instrumentation, Information, and Control Systems and Human-System Interface Technologies was held March 20–21, 2009, in Columbus, Ohio, to enable industry stakeholders and researchers in identification of the nuclear industry’s needs in the areas of future I&C technologies and corresponding technology gaps and research capabilities. Approaches for collaboration to bridge or fill the technology gaps were presented and R&D activities and priorities recommended. This report documents the presentations and discussions of the workshop and is intended to serve as a basis for the plan under development to achieve the goals of the I&C research pathway.

  13. International Conference on the Physics of Reactors "Nuclear Power: A Sustainable Resource" Casino-Kursaal Conference Center, Interlaken, Switzerland, September 14-19, 2008

    E-Print Network [OSTI]

    Boyer, Edmond

    International Conference on the Physics of Reactors "Nuclear Power: A Sustainable Resource" Casino International Forum for the new nuclear energy systems, we have developed a new concept of molten salt reactor Products which poison the core can be extracted without stopping reactor operation; nuclear waste

  14. SustainabilityStudies sustainability@uci.edu

    E-Print Network [OSTI]

    Rose, Michael R.

    SustainabilityStudies sustainability@uci.edu Sustainable Business Management Certificate Program in the sustainability field, such as managers, directors, architects, urban planners, landscape architects, designers opportunities and risks while minimizing potential liability. extension.uci.edu/sustainability Sustainable

  15. Sustainability

    Broader source: Energy.gov [DOE]

    Opening Plenary Session: Bioenergy Sustainability—Charting the Path toward a Viable Future Jody Endres, Assistant Professor, College of Agricultural, Consumer and Environmental Sciences, University of Illinois

  16. Sustainable Energy Fund (SEF) Loan Program (PPL Territory)

    Broader source: Energy.gov [DOE]

    The Sustainable Energy Fund (SEF) promotes and invests in energy efficiency and renewable energy projects, and energy education initiatives. Financial incentives are offered as loans to promote...

  17. ORNL/TM-2012/380 Roadmap for Nondestructive Evaluation of Reactor...

    Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

    by the Light Water Reactor Sustainability Program September 2012 Prepared by Cyrus Smith Randy Nanstad Robert Odette Dwight Clayton Katie Matlack Pradeep Ramuhalli Glenn Light...

  18. Sustainability Innovation in Research and Education (SIRE) Grants The request for proposals (RFP) for the Office of Sustainability's (OS) SIRE grants program will

    E-Print Network [OSTI]

    Sheridan, Jennifer

    Sustainability Innovation in Research and Education (SIRE) Grants The request for proposals (RFP) for the Office of Sustainability's (OS) SIRE grants program will be available around16 March 2012 in the Research in pursuing research or education initiatives in sustainability. The themes for 2012 are Buildings and Energy

  19. Reactor safety research programs. Quarterly report, January-March 1982

    SciTech Connect (OSTI)

    Edler, S.K. (ed.)

    1982-07-01T23:59:59.000Z

    This document summarizes work performed by Pacific Northwest Laboratory (PNL) from January 1 through March 31, 1982, for the Division of Accident Evaluation and the Division of Engineering Technology, US Nuclear Regulatory Commission (NRC). Evaluations of nondestructive examination (NDE) techniques and instrumentation are reported; areas of investigation include demonstrating the feasibility of determining the strength of structural graphite, evaluating the feasibility of detecting and analyzing flaw growth in reactor pressure boundary systems, examining NDE reliability and probabilistic fracture mechanics, and assessing the integrity of pressurized water reactor (PWR) steam generator tubes where service-induced degradation has been indicated. Experimental data and analytical models are being provided to aid in decision-making regarding pipe-to-pipe impacts following postulated breaks in high-energy fluid system piping. Core thermal models are being developed to provide better digital codes to compute the behavior of full-scale reactor systems under postulated accident conditions. Fuel assemblies and analytical support are being provided for experimental programs at other facilities.

  20. Reactor safety research programs. Quarterly report, April-June 1982

    SciTech Connect (OSTI)

    Edler, S.K. (ed.)

    1982-11-01T23:59:59.000Z

    This document summarizes work performed by Pacific Northwest Laboratory (PNL) from April 1 through June 30, 1982, for the Division of Accident Evaluation and the Division of Engineering Technology, US Nuclear Regulatory Commission (NRC). Evaluations of nondestructive examination (NDE) techniques and instrumentation are reported; areas of investigation include demonstrating the feasibility of determining the strength of structural graphite, evaluating the feasibility of detecting and analyzing flaw growth in reactor pressure boundary systems, examining NDE reliability and probabilistic fracture mechanics, and assessing the integrity of pressurized water reactor (PWR) steam generator tubes where service-induced degradation has been indicated. Experimental data and analytical models are being provided to aid in decision-making regarding pipe-to-pipe impacts following postulated breaks in high-energy fluid system piping. Core thermal models are being developed to provide better digital codes to compute the behavior of full-scale reactor systems under postulated accident conditions. Fuel assemblies and analytical support are being provided for experimental programs at other facilities.

  1. Sustaining the ADVANCE Program at the University of Wisconsin-Madison

    E-Print Network [OSTI]

    Sheridan, Jennifer

    Sustaining the ADVANCE Program at the University of Wisconsin-Madison Peter D. Spear Provost will be a visible, campus-wide entity, endorsed by top-level administrators, which will use UW-Madison as a "living;Sustaining ADVANCE--GOALS Intersections of WISELI goals/strategies with campus plans: Diversifying

  2. EIS-0085-S: Liquid-Metal Fast Breeder Reactor Program, Supplemental

    Broader source: Energy.gov [DOE]

    The U.S. Department of Energy developed this supplemental statement to examine the reduced scope of the Liquid Metal Fast Breeder Reactor (LMFBR) program and the environmental impacts associated therewith, including a re-examination of the purpose, need and timing of the program, the present program structure, including reasonable program alternatives, and alternative electricity production technologies anticipated to be available within the same timeframe as the LMFBR technology option. This statement supplements ERDA-1535, Liquid Metal Fast Breeder Reactor Program.

  3. Effect of heat recirculation on the self-sustained catalytic combustion of propane/air mixtures in a quartz reactor

    SciTech Connect (OSTI)

    Scarpa, A. [Dipartimento di Ingegneria Chimica, Universita degli Studi di Napoli ''Federico II'', P.le V. Tecchio 80, 80125 Naples (Italy); Department of Chemical Engineering, Center for Catalytic Science and Technology (CCST), and Center for Composite Materials (CCM), University of Delaware, 150 Academy Street, Newark, DE 19716 (United States); Pirone, R. [Istituto di Ricerche sulla Combustione-CNR, P.le V. Tecchio 80, 80125 Naples (Italy); Russo, G. [Dipartimento di Ingegneria Chimica, Universita degli Studi di Napoli ''Federico II'', P.le V. Tecchio 80, 80125 Naples (Italy); Vlachos, D.G. [Department of Chemical Engineering, Center for Catalytic Science and Technology (CCST), and Center for Composite Materials (CCM), University of Delaware, 150 Academy Street, Newark, DE 19716 (United States)

    2009-05-15T23:59:59.000Z

    The self-sustained catalytic combustion of propane is experimentally studied in a two-pass, quartz heat-recirculation reactor (HRR) and compared to that in a no (heat) recirculation reactor (NRR). Structured monolithic reactors with Pt/{gamma}-Al{sub 2}O{sub 3}, LaMnO{sub 3}/{gamma}-Al{sub 2}O{sub 3}, and Pt doped perovskite catalysts have been compared in the HRR and NRR configurations. Heat recirculation enhances combustion stability, by widening the operating window of self-sustained operation, and changes the mode of stability loss from blowout to extinction. It is found that thermal shields (upstream and downstream of the monolith) play no role in the stability of a HRR but increase the stability of a NRR. The stability of a HRR follows this trend: Pt/{gamma}-Al{sub 2}O{sub 3} > doped perovskite > LaMnO{sub 3}/{gamma}-Al{sub 2}O{sub 3}. Finally, a higher cell density monolith enlarges the operating window of self-sustained combustion, and allows further increase of the power density of the process. (author)

  4. Miami-Dade County- Sustainable Buildings Program (Florida)

    Broader source: Energy.gov [DOE]

    In 2005, the Miami-Dade Board of County Commissioners passed a [http://www.miamidade.gov/govaction/matter.asp?matter=052213&file=true&ye... resolution] to incorporate sustainable building...

  5. City of San Diego- Sustainable Building Expedited Permit Program

    Broader source: Energy.gov [DOE]

    In 2002, the City of San Diego passed a Resolution R-298001, which amended the [http://dsireusa.org/incentives/incentive.cfm?Incentive_Code=CA42R&re=1&ee=1 Sustainable Building Policy] to...

  6. Sustainable Military Lands Enroll in this one-of-a-kind online educational program to learn the

    E-Print Network [OSTI]

    Sustainable Military Lands Management Enroll in this one-of-a-kind online educational program. Designed for both civilian and military land management professionals, the Sustainable Military Lands Management (SMLM) certificate program gives you the key concepts for conservation and sustainable management

  7. (COMEDIE program review and fission product transport in MHTGR reactor)

    SciTech Connect (OSTI)

    Stansfield, O.M.

    1990-03-15T23:59:59.000Z

    The subcontract between Martin Marietta Energy Systems, Inc., and the CEA provides for the refurbishment of the high pressure COMEDIE test loop in the SILOE reactor and a series of experiments to characterize fission product lift-off from MHTGR heat exchanger surfaces under several depressurization accident scenarios. The data will contribute to the validation of models and codes used to predict fission product transport in the MHTGR. In the meeting at CEA headquarters in Paris the program schedule and preparation for the DCAA and Quality Assurance audits were discussed. Long-range interest in expanded participation in the gas-cooled reactor technology Umbrella Agreement was also expressed by the CEA. At the CENG, in Grenoble, technical details on the loop design, fabrication components, development of test procedures, and preparation for the DOE quality assurance (QA) audit in May were discussed. After significant delays in CY 1989 it appears that good progress is being made in CY 1990 and the first major test will be initiated by December. An extensive list of agreements and commitments was generated to facilitate the coordination and planning of future work. 2 figs., 2 tabs.

  8. US Department of Energy 1992--1993 Reactor Sharing Program. Final report

    SciTech Connect (OSTI)

    Vernetson, W.G.

    1994-04-01T23:59:59.000Z

    The University of Florida Training Reactor serves as a host institution to support various educational institutions which are located primarily within the state of Florida. All users and uses were carefully screened to assure the usage was for educational institutions eligible for participation in the Reactor Sharing Program. Three tables are included that provide basic information about the 1992--1993 program and utilization of the reactor facilities by user institutions.

  9. Program Sustainability Peer Exchange Call: Transitioning to a...

    Office of Energy Efficiency and Renewable Energy (EERE) Indexed Site

    program costs into its rate design, it is difficult for it to get involved in demand side management, rebates, etc. In addition to program cost recovery, utilities need a...

  10. Austin's Green Building Program: A Tool for Sustainable Development

    E-Print Network [OSTI]

    Seiter, D. L.

    1994-01-01T23:59:59.000Z

    presented by the Association of Demand Side Management Professionals in November, 1993. This paper will follow the implementation and operation of the Green Building Program, with discussions on the successes, challenges, and modifications of the program...

  11. Golden Valley Electric Association- Sustainable Natural Alternative Power (SNAP) Program

    Broader source: Energy.gov [DOE]

    Golden Valley Electric Association's (GVEA) SNAP program encourages members to install renewable energy generators and connect them to the utility's electrical distribution system by offering an...

  12. 2013 EL Program: Sustainable Manufacturing Program Manager: Dr. Sudarsan Rachuri, 301 975 4264

    E-Print Network [OSTI]

    Bentz, Dale P.

    U.S. companies summarizing their efforts to improve sustainable business practices. According-to-gate is a partial LCA looking at only one value-added process in the entire production chain. 5 The Sustainability. To plan for these changes, they are building business cases for sustainability. In building these cases

  13. Light Water Reactor Safety Research Program. Semiannual report, April-September 1982

    SciTech Connect (OSTI)

    Berman, M.

    1983-10-01T23:59:59.000Z

    This report documents progress made in Light Water Reactor Safety research conducted by Division 6441 in the period from April 1982 to September 1982. The programs conducted under investigation include Core Concrete Interactions, Core Melt-Coolant Interactions, Containment Emergency Sump Performance, the Hydrogen Program, and Combustible Gas in Containment Program. 50 references.

  14. UCLA program in reactor studies: The ARIES tokamak reactor study. Progress report, December 1, 1990--November 30, 1991

    SciTech Connect (OSTI)

    Not Available

    1991-12-01T23:59:59.000Z

    The ARIES research program is a multi-institutional effort to develop several visions of tokamak reactors with enhanced economic, safety, and environmental features. The aims are to determine the potential economics, safety, and environmental features of a range of possible tokamak reactors, and to identify physics and technology areas with the highest leverage for achieving the best tokamak reactor. Four ARIES visions are currently planned for the ARIES program. The ARIES-1 design is a DT-burning reactor based on ``modest`` extrapolations from the present tokamak physics database and relies on either existing technology or technology for which trends are already in place, often in programs outside fusion. ARIES-2 and ARIES-4 are DT-burning reactors which will employ potential advances in physics. The ARIES-2 and ARIES-4 designs employ the same plasma core but have two distinct fusion power core designs; ARIES-2 utilize the lithium as the coolant and breeder and vanadium alloys as the structural material while ARIES-4 utilizes helium is the coolant, solid tritium breeders, and SiC composite as the structural material. Lastly, the ARIES-3 is a conceptual D-{sup 3}He reactor. During the period Dec. 1, 1990 to Nov. 31, 1991, most of the ARIES activity has been directed toward completing the technical work for the ARIES-3 design and documenting the results and findings. We have also completed the documentation for the ARIES-1 design and presented the results in various meetings and conferences. During the last quarter, we have initiated the scoping phase for ARIES-2 and ARIES-4 designs.

  15. Track 4: Sustainability in National Programs I. Impact of Executive Orders on Federal Agencies

    E-Print Network [OSTI]

    . Energy Conservation in Infrastructure 1. Impact of Executive Orders on Federal Agencies: Two presidential executive orders have expanded federal agencies' responsibility for energy efficiency, renewable energy1 Track 4: Sustainability in National Programs I. Impact of Executive Orders on Federal Agencies II

  16. SAMPLE INTERNSHIP DESCRIPTION NOT CURRENTLY OPEN FOR INFORMATION ONLY Sustainable Communities Immersion Program Internship

    E-Print Network [OSTI]

    to the student's school schedule, must be available Mon-Fri business hours. 8 hours per week to start. Location audit Directing marketing efforts to target neighborhoods Promoting sustainability program We'd rather,) and online resources Highly motivated self-starter and high energy level with demonstrated ability to take

  17. GCRA review and appraisal of HTGR reactor-core-design program. [HTGR-SC, -R, -NHSDR

    SciTech Connect (OSTI)

    Not Available

    1980-09-01T23:59:59.000Z

    The reactor-core-design program has as its principal objective and responsibility the design and resolution of major technical issues for the reactor core and core components on a schedule consistent with the plant licensing and construction program. The task covered in this review includes three major design areas: core physics, core thermal and hydraulic performance fuel element design, and in-core fuel performance evaluation.

  18. Sustainable UMass Green Office Program: Certification Checklist Office: Eco Leader

    E-Print Network [OSTI]

    Massachusetts at Amherst, University of

    or are programmed to shut off through a timer Waste & Recycling: Prerequisites WP1 We have a designated area in our, printers, A/V, office phones, etc.) to the Office of Waste Management for proper recycling W6 We have percent post-consumer recycled content K3 We only offer organic and/or f

  19. 2014 APSECA Safe Programming Guidance of Function Block Diagram for Reactor Protection Systems Dong-Ah Lee*, Junbeom Yoo

    E-Print Network [OSTI]

    Diagram for Reactor Protection Systems (1/5) Execution control except EN and ENO signals ¡ Boolean "EN2014 APSECA Safe Programming Guidance of Function Block Diagram for Reactor Protection Systems Dong for the Use of Function Block Diagram in Reactor Protection Systems #12;2014 APSECA Safe Programming Guidance

  20. GLOBAL THREAT REDUCTION INITIATIVE REACTOR CONVERSION PROGRAM: STATUS AND CURRENT PLANS

    SciTech Connect (OSTI)

    Staples, Parrish A.; Leach, Wayne; Lacey, Jennifer M.

    2009-10-07T23:59:59.000Z

    The U.S. Department of Energy’s National Nuclear Security Administration (NNSA) Reactor Conversion Program supports the minimization, and to the extent possible, elimination of the use of high enriched uranium (HEU) in civilian nuclear applications by working to convert research and test reactors and radioisotope production processes to the use of low enriched uranium (LEU). The Reactor Conversion Program is a technical pillar of the NNSA Global Threat Reduction Initiative (GTRI) which is a key organization for implementing U.S. HEU minimization policy and works to reduce and protect vulnerable nuclear and radiological material domestically and abroad.

  1. RERTR Program: goals, progress and plans. [Reduced Enrichment Research and Test Reactor

    SciTech Connect (OSTI)

    Travelli, A.

    1984-09-25T23:59:59.000Z

    The status of the US Reduced Enrichment Research and Test Reactor (RERTR) Program is reviewed. After a brief outline of RERTR Program objectives and goals, program accomplishments are discussed with emphasis on the development, demonstration and application of new LEU fuels. Most program activities have proceeded as planned, and a combination of two silicide fuels (U/sub 3/Si/sub 2/-Al and U/sub 3/Si-Al) holds excellent promise for achieving the long-term program goals. Current plans and schedules project the uranium density of qualified RERTR fuels for plate-type reactors to grow by approximately 1 g U/cm/sup 3/ each year, from the nearly null value of 1982 to the 7.0 g U/cm/sup 3/ which will be reached in early 1989. The technical needs of research reactors for HEU exports are also estimated to undergo a gradual but dramatic decline in the coming years.

  2. Recovery Act - Sustainable Transportation: Advanced Electric Drive Vehicle Education Program

    SciTech Connect (OSTI)

    Caille, Gary

    2013-12-13T23:59:59.000Z

    The collective goals of this effort include: 1) reach all facets of this society with education regarding electric vehicles (EV) and plug–in hybrid electric vehicles (PHEV), 2) prepare a workforce to service these advanced vehicles, 3) create web–based learning at an unparalleled level, 4) educate secondary school students to prepare for their future and 5) train the next generation of professional engineers regarding electric vehicles. The Team provided an integrated approach combining secondary schools, community colleges, four–year colleges and community outreach to provide a consistent message (Figure 1). Colorado State University Ventures (CSUV), as the prime contractor, plays a key program management and co–ordination role. CSUV is an affiliate of Colorado State University (CSU) and is a separate 501(c)(3) company. The Team consists of CSUV acting as the prime contractor subcontracted to Arapahoe Community College (ACC), CSU, Motion Reality Inc. (MRI), Georgia Institute of Technology (Georgia Tech) and Ricardo. Collaborators are Douglas County Educational Foundation/School District and Gooru (www.goorulearning.org), a nonprofit web–based learning resource and Google spin–off.

  3. Benchmark Evaluation of the Medium-Power Reactor Experiment Program Critical Configurations

    SciTech Connect (OSTI)

    Margaret A. Marshall; John D. Bess

    2013-02-01T23:59:59.000Z

    A series of small, compact critical assembly (SCCA) experiments were performed in 1962-1965 at the Oak Ridge National Laboratory Critical Experiments Facility (ORCEF) for the Medium-Power Reactor Experiment (MPRE) program. The MPRE was a stainless-steel clad, highly enriched uranium (HEU)-O2 fuelled, BeO reflected reactor design to provide electrical power to space vehicles. Cooling and heat transfer were to be achieved by boiling potassium in the reactor core and passing vapor directly through a turbine. Graphite- and beryllium-reflected assemblies were constructed at ORCEF to verify the critical mass, power distribution, and other reactor physics measurements needed to validate reactor calculations and reactor physics methods. The experimental series was broken into three parts, with the third portion of the experiments representing the beryllium-reflected measurements. The latter experiments are of interest for validating current reactor design efforts for a fission surface power reactor. The entire series has been evaluated as acceptable benchmark experiments and submitted for publication in the International Handbook of Evaluated Criticality Safety Benchmark Experiments and in the International Handbook of Evaluated Reactor Physics Benchmark Experiments.

  4. Reactor Safety Research: Semiannual report, January-June 1986: Reactor Safety Research Program

    SciTech Connect (OSTI)

    Not Available

    1987-05-01T23:59:59.000Z

    Sandia National Laboratories is conducting, under USNRC sponsorship, phenomenological research related to the safety of commercial nuclear power reactors. The research includes experiments to simulate the phenomenology of accident conditions and the development of analytical models, verified by experiment, which can be used to predict reactor and safety systems performance behavior under abnormal conditions. The objective of this work is to provide NRC requisite data bases and analytical methods to (1) identify and define safety issues, (2) understand the progression of risk-significant accident sequences, and (3) conduct safety assessments. The collective NRC-sponsored effort at Sandia National Laboratories is directed at enhancing the technology base supporting licensing decisions.

  5. Participation in the United States Department of Energy Reactor Sharing Program

    SciTech Connect (OSTI)

    Mulder, R.U.; Benneche, P.E.; Hosticka, B.

    1992-12-01T23:59:59.000Z

    The University of Virginia Reactor Facility is an integral part of the Department of Mechanical, Aerospace and Nuclear Engineering and is used to support educational programs in engineering and science at the University of Virginia and at other area colleges and universities. The University of Virginia Research Reactor (UVAR) is the highest power (two megawatts thermal power) and one of the most utilized university research reactor in the mid-Atlantic states. A major objective of this facility is to support educational programs in the region. The University of Virginia has received support under the US Department of Energy (DOE) Reactor Sharing Program every year since 1978 to assist in meeting this objective. This report documents the major educational accomplishments under the Reactor Sharing Program for the period September 1991 through August 1992. This report is also to final report under this contract. Previous annual reports should be consulted if any information from those periods is desired. Additional information about the programs conducted at UVA under this contract may be found in the yearly requests for additional funds which have been submitted.

  6. Using low-enriched uranium in research reactors: The RERTR program

    SciTech Connect (OSTI)

    Travelli, A.

    1994-05-01T23:59:59.000Z

    The goal of the RERTR program is to minimize and eventually eliminate use of highway enriched uranium (HEU) in research and test reactors. The program has been very successful, and has developed low-enriched uranium (LEU) fuel materials and designs which can be used effectively in approximately 90 percent of the research and test reactors which used HEU when the program began. This progress would not have been possible without active international cooperation among fuel developers, commercial vendors, and reactor operators. The new tasks which the RERTR program is undertaking at this time include development of new and better fuels that will allow use of LEU fuels in all research and test reactors; cooperation with Russian laboratories, which will make it possible to minimize and eventually eliminate use of HEU in research reactors throughout the world, irrespective of its origin; and development of an LEU-based process for the production of {sup 99}Mo. Continuation and intensification of international cooperation are essential to the achievement of the ultimate goals of the RERTR program.

  7. Plutonium Consumption Program, CANDU Reactor Project final report

    SciTech Connect (OSTI)

    Not Available

    1994-07-31T23:59:59.000Z

    DOE is investigating methods for long term dispositioning of weapons grade plutonium. One such method would be to utilize the plutonium in Mixed OXide (MOX) fuel assemblies in existing CANDU reactors. CANDU (Canadian Deuterium Uranium) reactors are designed, licensed, built, and supported by Atomic Energy of Canada Limited (AECL), and currently use natural uranium oxide as fuel. The MOX spent fuel assemblies removed from the reactor would be similar to the spent fuel currently produced using natural uranium fuel, thus rendering the plutonium as unattractive as that in the stockpiles of commercial spent fuel. This report presents the results of a study sponsored by the DOE for dispositioning the plutonium using CANDU technology. Ontario Hydro`s Bruce A was used as reference. The fuel design study defined the optimum parameters to disposition 50 tons of Pu in 25 years (or 100 tons). Two alternate fuel designs were studied. Safeguards, security, environment, safety, health, economics, etc. were considered. Options for complete destruction of the Pu were also studied briefly; CANDU has a superior ability for this. Alternative deployment options were explored and the potential impact on Pu dispositioning in the former Soviet Union was studied. An integrated system can be ready to begin Pu consumption in 4 years, with no changes required to the reactors other than for safe, secure storage of new fuel.

  8. U.S. Department of Energy Program of International Technical Cooperation for Research Reactor Utilization

    SciTech Connect (OSTI)

    Chong, D.; Manning, M.; Ellis, R.; Apt, K.; Flaim, S.; Sylvester, K.

    2004-10-03T23:59:59.000Z

    The U.S. Department of Energy, National Nuclear Security Administration (DOE/NNSA) has initiated collaborations with the national nuclear authorities of Egypt, Peru, and Romania for the purpose of advancing the commercial potential and utilization of their respective research reactors. Under its Office of International Safeguards ''Sister Laboratory'' program, DOE/NNSA has undertaken numerous technical collaborations over the past decade intended to promote peaceful applications of nuclear technology. Among these has been technical assistance in research reactor applications, such as neutron activation analysis, nuclear analysis, reactor physics, and medical radioisotope production. The current collaborations are intended to provide the subject countries with a methodology for greater commercialization of research reactor products and services. Our primary goal is the transfer of knowledge, both in administrative and technical issues, needed for the establishment of an effective business plan and utilization strategy for the continued operation of the countries' research reactors. Technical consultation, cooperation, and the information transfer provided are related to: identification, evaluation, and assessment of current research reactor capabilities for products and services; identification of opportunities for technical upgrades for new or expanded products and services; advice and consultation on research reactor upgrades and technical modifications; characterization of markets for reactor products and services; identification of competition and estimation of potential for market penetration; integration of technical constraints; estimation of cash flow streams; and case studies.

  9. What Makes Development Sustainable? Case Studies of Health and Human Development Programs in Community Context

    E-Print Network [OSTI]

    Saha, Somava

    1996-01-01T23:59:59.000Z

    of Institutions. ” Making Development Sustainable: Rede?ningIs to Be Done? ” Making Development Sustainable: RedefiningManagement and Sustainable Development. ” Ambio 18.2 (1989):

  10. What Makes Development Sustainable? Case Studies of Health and Human Development Programs in Community Context

    E-Print Network [OSTI]

    Saha, Somava

    1996-01-01T23:59:59.000Z

    Management and Sustainable Development. ” Ambio 18.2 (1989):Sandbrook, Richard. ”Sustainable Development: What Is to Be3. Redclift, Michael. Sustainable Development: Exploring the

  11. Progress of the RERTR (Reduced Enrichment Research and Test Reactor) Program in 1989

    SciTech Connect (OSTI)

    Travelli, A.

    1989-01-01T23:59:59.000Z

    The progress of the Reduced Enrichment Research and Test Reactor (RERTR) Program is described. After a brief summary of the results which the RERTR Program, in collaboration with its many international partners, had achieved by the end of 1988, the major events, findings, and activities of 1989 are reviewed. The scope of the RERTR Program activities was curtailed, in 1989, by an unexpected legislative restriction which limited the ability of the Arms Control and Disarmament Agency to adequately fund the program. Nevertheless, the thrust of the major planned program activities was maintained, and meaningful results were obtained in several areas of great significance for future work. 15 refs., 12 figs.

  12. FFTF and Advanced Reactors Transition Program Resource Loaded Schedule

    SciTech Connect (OSTI)

    GANTT, D.A.

    2000-10-31T23:59:59.000Z

    This Resource Load Schedule (RLS) addresses two missions. The Advanced Reactors Transition (ART) mission, funded by DOE-EM, is to transition assigned, surplus facilities to a safe and compliant, low-cost, stable, deactivated condition (requiring minimal surveillance and maintenance) pending eventual reuse or D&D. Facilities to be transitioned include the 309 Building Plutonium Recycle Test Reactor (PRTR) and Nuclear Energy Legacy facilities. This mission is funded through the Environmental Management (EM) Project Baseline Summary (PBS) RL-TP11, ''Advanced Reactors Transition.'' The second mission, the Fast Flux Test Facility (FFTF) Project, is funded through budget requests submitted to the Office of Nuclear Energy, Science and Technology (DOE-NE). The FFTF Project mission is maintaining the FFTF, the Fuels and Materials Examination Facility (FMEF), and affiliated 400 Area buildings in a safe and compliant standby condition. This mission is to preserve the condition of the plant hardware, software, and personnel in a manner not to preclude a plant restart. This revision of the Resource Loaded Schedule (RLS) is based upon the technical scope in the latest revision of the following project and management plans: Fast Flux Test Facility Standby Plan (Reference 1); Hanford Site Sodium Management Plan (Reference 2); and 309 Building Transition Plan (Reference 4). The technical scope, cost, and schedule baseline is also in agreement with the concurrent revision to the ART Fiscal Year (FY) 2001 Multi-Year Work Plan (MYWP), which is available in an electronic version (only) on the Hanford Local Area Network, within the ''Hanford Data Integrator (HANDI)'' application.

  13. Standard Practice for Design of Surveillance Programs for Light-Water Moderated Nuclear Power Reactor Vessels

    E-Print Network [OSTI]

    American Society for Testing and Materials. Philadelphia

    2010-01-01T23:59:59.000Z

    1.1 This practice covers procedures for designing a surveillance program for monitoring the radiation-induced changes in the mechanical properties of ferritic materials in light-water moderated nuclear power reactor vessels. This practice includes the minimum requirements for the design of a surveillance program, selection of vessel material to be included, and the initial schedule for evaluation of materials. 1.2 This practice was developed for all light-water moderated nuclear power reactor vessels for which the predicted maximum fast neutron fluence (E > 1 MeV) at the end of license (EOL) exceeds 1 × 1021 neutrons/m2 (1 × 1017 n/cm2) at the inside surface of the reactor vessel. 1.3 This practice applies only to the planning and design of surveillance programs for reactor vessels designed and built after the effective date of this practice. Previous versions of Practice E185 apply to earlier reactor vessels. 1.4 This practice does not provide specific procedures for monitoring the radiation induced cha...

  14. A mathematical method for boiling water reactor control rod programming

    SciTech Connect (OSTI)

    Tokumasu, S.; Hiranuma, H.; Ozawa, M.; Yokomi, M.

    1985-12-01T23:59:59.000Z

    A new mathematical programming method has been developed and utilized in OPROD, an existing computer code for automatic generation of control rod programs as an alternative inner-loop routine for the method of approximate programming. The new routine is constructed of a dual feasible direction algorithm, and consists essentially of two stages of iterative optimization procedures Optimization Procedures I and II. Both follow almost the same algorithm; Optimization Procedure I searches for feasible solutions and Optimization Procedure II optimizes the objective function. Optimization theory and computer simulations have demonstrated that the new routine could find optimum solutions, even if deteriorated initial control rod patterns were given.

  15. Participation in the United States Department of Energy Reactor Sharing Program

    SciTech Connect (OSTI)

    Mulder, R.U.; Benneche, P.E.; Hosticka, B.

    1992-05-01T23:59:59.000Z

    The University of Virginia Reactor Facility is an integral part of the Department of Nuclear Engineering and Engineering Physics (to become the Department of Mechanical, Aerospace and Nuclear Engineering on July 1, 1992). As such, it is effectively used to support educational programs in engineering and science at the University of Virginia as well as those at other area colleges and universities. The expansion of support to educational programs in the mid-east region is a major objective. To assist in meeting this objective, the University of Virginia has been supported under the US Department of Energy (DOE) Reactor Sharing Program since 1978. Due to the success of the program, this proposal requests continued DOE support through August 1993.

  16. Human-In-The-Loop Simulation in Support of Long-Term Sustainability of Light Water Reactors

    SciTech Connect (OSTI)

    Bruce P Hallbert

    2015-01-01T23:59:59.000Z

    Reliable instrumentation, information, and control systems technologies are essential to ensuring safe and efficient operation of the U.S. light water reactor (LWR) fleet. These technologies affect every aspect of nuclear power plant (NPP) and balance-of-plant operations. In 1997, the National Research Council conducted a study concerning the challenges involved in modernization of digital instrumentation and control systems in NPPs. Their findings identified the need for new II&C technology integration. The NPP owners and operators realize that this analog technology represents a significant challenge to sustaining the operation of the current fleet of NPPs. Beyond control systems, new technologies are needed to monitor and characterize the effects of aging and degradation in critical areas of key structures, systems, and components. The objective of the efforts sponsored by the U.S. Department of Energy is to develop, demonstrate, and deploy new digital technologies for II&C architectures and provide monitoring capabilities to ensure the continued safe, reliable, and economic operation of the nation’s NPPs.

  17. Sustainable Stanford Greening Infrastructure & Choices

    E-Print Network [OSTI]

    sustainability coordinators Work with Office of Sustainability as staff to assist and coordinate with building;1717 Building Level Conservation Solicit participation for the campus Building Level Sustainability Program #12Sustainable Stanford Greening Infrastructure & Choices Fahmida Ahmed Office of Sustainability #12

  18. Received two 2013 Sustainability Awards from DOE for "Sustainable Campus" and "Innovative and Holistic Sustainability." PNNL advances the DOE sustainability

    E-Print Network [OSTI]

    Received two 2013 Sustainability Awards from DOE for "Sustainable Campus" and "Innovative and Holistic Sustainability." PNNL advances the DOE sustainability mission with a diverse, focused effort toward goals for 2020 and beyond. The Sustainability Program and Information Management Services put

  19. Light water reactor safety research program. Volume 12: quarterly report, Apr-Jun 79

    SciTech Connect (OSTI)

    Berman, M.

    1980-05-01T23:59:59.000Z

    This report summarizes the progress of the Light Water Reactor Safety Research Program during the 2nd quarter of 1979. Specifically, the report summarizes progress in five major areas of research. They are: (1) the molten core/concrete interactions study; (2) steam explosion research phenomena; (3) statistical LOCA analysis; (4) UHI model development; (5) two-phase jet loads.

  20. Light-Water-Reactor Safety Research Program. Quarterly progress report, October-December 1979

    SciTech Connect (OSTI)

    Massey, W.E.; Kyger, J.A.

    1980-05-01T23:59:59.000Z

    This progress report summarizes the Argonne National Laboratory work performed during October, November, and December 1979 on water-reactor-safety problems. The research and development areas covered are: (1) Heat Transfer Coordination for LOCA Research Programs and (2) Transient Fuel Response and Fission-Product Release. 29 refs., 39 figs., 1 tab.

  1. The RERTR (Reduced Enrichment Research and Test Reactor) program: A progress report

    SciTech Connect (OSTI)

    Travelli, A.

    1986-11-01T23:59:59.000Z

    The progress of the Reduced Enrichment Research and Test Reactor (RERTR) Program is described. After a brief summary of the results which the RERTR Program, in collaboration with its many international partners, had achieved by the end of 1985, the activities, results, and new developments which occurred in 1986 are reviewed. The second miniplate series, concentrating on U/sub 3/Si/sub 2/-Al and U/sub 3/Si-Al fuels, was expanded and its irradiation continued. Postirradiation examinations of several of these miniplates and of six previously irradiated U/sub 3/Si/sub 2/-Al full-size elements were completed with excellent results. The whole-core ORR demonstration with U/sub 3/Si/sub 2/-Al fuel at 4.8 g U/cm/sup 3/ is well under way and due for completion before the end of 1987. DOE removed an important barrier to conversions by announcing that the new LEU fuels will be accepted for reprocessing. New DOE prices for enrichment and reprocessing services were calculated to have minimal effect on HEU reactors, and to reduce by about 8 to 10% the total fuel cycle costs of LEU reactors. New program activities include preliminary feasibility studies of LEU use in DOE reactors, evaluation of the feasibility to use LEU targets for the production of fission-product /sup 99/Mo, and responsibility for coordinating safety evaluations related to LEU conversions of US university reactors, as required by NRC. Achievement of the final program goals is projected for 1990. This progress could not have been achieved without close international cooperation, whose continuation and intensification are essential to the achievement of the ultimate goals of the RERTR Program.

  2. Los Alamos National Laboratory and Lawrence Livermore National Laboratory Plutonium Sustainment Monthly Program Report September 2012

    SciTech Connect (OSTI)

    McLaughlin, Anastasia Dawn [Los Alamos National Laboratory; Storey, Bradford G. [Los Alamos National Laboratory; Bowidowicz, Martin [Los Alamos National Laboratory; Robertson, William G. [Los Alamos National Laboratory; Hobson, Beverly F. [Los Alamos National Laboratory

    2012-10-22T23:59:59.000Z

    In March of 2012 the Plutonium Sustainment program at LANL completed or addressed the following high-level activities: (1) Delivered Revision 2 of the Plutonium Sustainment Manufacturing Study, which incorporated changes needed due to the release of the FY2013 President's Budget and the delay in the Chemistry and Metallurgy Research Replacement Nuclear Facility (CMRRNF). (2) W87 pit type development activities completed a detailed process capability review for the flowsheet in preparation for the Engineering Development Unit Build. (3) Completed revising the Laser Beam Welding schedule to address scope and resource changes. (4) Completed machining and inspecting the first set of high-fidelity cold parts on Precitech 2 for Gemini. (5) The Power Supply Assembly Area started floor cutting with a concrete saw and continued legacy equipment decommissioning. There are currently no major issues associated with achieving MRT L2 Milestones 4195-4198 or the relevant PBIs associated with Plutonium Sustainment. There are no budget issues associated with FY12 final budget guidance. Table 1 identifies all Baseline Change Requests (BCRs) that were initiated, in process, or completed during the month. The earned value metrics overall for LANL are within acceptable thresholds, so no high-level recovery plan is required. Each of the 5 major LANL WBS elements is discussed in detail.

  3. The current state of the Russian reduced enrichment research reactors program

    SciTech Connect (OSTI)

    Aden, V.G.; Kartashov, E.F.; Lukichev, V.A. [and others

    1997-08-01T23:59:59.000Z

    During the last year after the 16-th International Conference on Reducing Fuel Enrichment in Research Reactors held in October, 1993 in Oarai, Japan, the conclusive stage of the Program on reducing fuel enrichment (to 20% in U-235) in research reactors was finally made up in Russia. The Program was started late in 70th and the first stage of the Program was completed by 1986 which allowed to reduce fuel enrichment from 80-90% to 36%. The completion of the Program current stage, which is counted for 5-6 years, will exclude the use of the fuel enriched by more than 20% from RF to other countries such as: Poland, Czeck Republick, Hungary, Roumania, Bulgaria, Libya, Viet-Nam, North Korea, Egypt, Latvia, Ukraine, Uzbekistan and Kazakhstan. In 1994 the Program, approved by RF Minatom authorities, has received the status of an inter-branch program since it was admitted by the RF Ministry for Science and Technical Policy. The Head of RF Minatom central administrative division N.I.Ermakov was nominated as the Head of the Russian Program, V.G.Aden, RDIPE Deputy Director, was nominated as the scientific leader. The Program was submitted to the Commission for Scientific, Technical and Economical Cooperation between USA and Russia headed by Vice-President A. Gore and Prime Minister V. Chemomyrdin and was given support also.

  4. Reactor safety research programs. Quarterly report, January-March 1985. Volume 1

    SciTech Connect (OSTI)

    Edler, S.K. (ed.)

    1985-08-01T23:59:59.000Z

    This document summarizes work performed by Pacific Northwest Laboratory from January 1 through March 31, 1985, for the Division of Accident Evaluation and the Division of Engineering Technology, US Nuclear Regulatory Commission. Results from an instrumented fuel assembly irradiation program being performed at Halden, Norway, are reported. Experimental data and analytical models are being provided to aid in decision making regarding pipe-to-pipe impacts following postulated breaks in high-energy fluid system piping. Fuel assemblies and analytical support are being provided for experimental programs at the Power Burst Facility, Idaho National Engineering Laboratory, Idaho Falls, Idaho. High-temperature materials property tests are being conducted to provide data on severe core damage fuel behavior. Thermal-hydraulic computer programs are providing best-estimate analyses for a variety of safety issues in light-water reactors. Severe fuel damage tests are being conducted in the NRU Reactor, Chalk River, Canada.

  5. University of Florida--US Department of Energy 1994-1995 reactor sharing program

    SciTech Connect (OSTI)

    Vernetson, W.G.

    1996-06-01T23:59:59.000Z

    The grant support of $24,250 (1994-95?) was well used by the University of Florida as host institution to support various educational institutions in the use of UFTR Reactor. All users and uses were screened to assure the usage was for educational institutions eligible for participation in the Reactor Sharing Program; where research activities were involved, care was taken to assure the research was not funded by grants for contract funding from outside sources. Over 12 years, the program has been a key catalyst for renewing utilization of UFTR both by external users around the State of Florida and the Southeast and by various faculty members within the University of Florida. Tables provide basic information about the 1994-95 program and utilization of UFTR.

  6. High-temperature gas-cooled reactor (HTGR): long term program plan

    SciTech Connect (OSTI)

    Not Available

    1980-10-09T23:59:59.000Z

    The FY 1980 effort was to investigate four technology options identified by program participants as potentially viable candidates for near-term demonstration: the Gas Turbine system (HTGR-GT), reflecting its perceived compatibility with the dry-cooling market, two systems addressing the process heat market, the Reforming (HTGR-R) and Steam Cycle (HTGR-SC) systems, and a more developmental reactor system, The Nuclear Heat Source Demonstration Reactor (NHSDR), which was to serve as a basis for both the HTGR-GT and HTGR-R systems as well as the further potential for developing advanced applications such as steam-coal gasification and water splitting.

  7. Gas-cooled reactor programs. High-temperature gas-cooled reactor technology development program. Annual progress report, December 31, 1983

    SciTech Connect (OSTI)

    Kasten, P.R.; Rittenhouse, P.L.; Bartine, D.E.; Sanders, J.P.

    1984-06-01T23:59:59.000Z

    ORNL continues to make significant contributions to the national program. In the HTR fuels area, we are providing detailed statistical information on the fission product retention performance of irradiated fuel. Our studies are also providing basic data on the mechanical, physical, and chemical behavior of HTR materials, including metals, ceramics, graphite, and concrete. The ORNL has an important role in the development of improved HTR graphites and in the specification of criteria that need to be met by commercial products. We are also developing improved reactor physics design methods. Our work in component development and testing centers in the Component Flow Test Loop (CFTL), which is being used to evaluate the performance of the HTR core support structure. Other work includes experimental evaluation of the shielding effectiveness of the lower portions of an HTR core. This evaluation is being performed at the ORNL Tower Shielding Facility. Researchers at ORNL are developing welding techniques for attaching steam generator tubing to the tubesheets and are testing ceramic pads on which the core posts rest. They are also performing extensive testing of aggregate materials obtained from potential HTR site areas for possible use in prestressed concrete reactor vessels. During the past year we continued to serve as a peer reviewer of small modular reactor designs being developed by GA and GE with balance-of-plant layouts being developed by Bechtel Group, Inc. We have also evaluated the national need for developing HTRs with emphasis on the longer term applications of the HTRs to fossil conversion processes.

  8. Reactor-safety research programs. Quarterly report, October-December 1982. Volume 4

    SciTech Connect (OSTI)

    Edler, S.K. (ed.)

    1983-04-01T23:59:59.000Z

    Evaluations of nondestructive examination (NDE) techniques and instrumentation are reported; areas of investigation include demonstrating the feasibility of determining the strength of structural graphite, evaluating the feasibility of detecting and analyzing flaw growth in reactor pressure boundary systems, examining NDE reliability and probabilistic fracture mechanics, and assessing the integrity of pressurized-water-reactor steam-generator tubes where service-induced degradation has been indicated. Experimental data and analytical models are being provided to aid in decision making regarding pipe-to-pipe impacts following postulated breaks in high-energy fluid system piping. Core thermal models being developed to provide better digital codes to compute the bahavior of full-scale reactor systems under postulated accident conditions. Fuel assemblies and analytical support are being provided for experimental programs at other facilities.

  9. Updated Generation IV Reactors Integrated Materials Technology Program Plan, Revision 2

    SciTech Connect (OSTI)

    Corwin, William R [ORNL; Burchell, Timothy D [ORNL; Halsey, William [Lawrence Livermore National Laboratory (LLNL); Hayner, George [Idaho National Laboratory (INL); Katoh, Yutai [ORNL; Klett, James William [ORNL; McGreevy, Timothy E [ORNL; Nanstad, Randy K [ORNL; Ren, Weiju [ORNL; Snead, Lance Lewis [ORNL; Stoller, Roger E [ORNL; Wilson, Dane F [ORNL

    2005-12-01T23:59:59.000Z

    The Department of Energy's (DOE's) Generation IV Nuclear Energy Systems Program will address the research and development (R&D) necessary to support next-generation nuclear energy systems. Such R&D will be guided by the technology roadmap developed for the Generation IV International Forum (GIF) over two years with the participation of over 100 experts from the GIF countries. The roadmap evaluated over 100 future systems proposed by researchers around the world. The scope of the R&D described in the roadmap covers the six most promising Generation IV systems. The effort ended in December 2002 with the issue of the final Generation IV Technology Roadmap [1.1]. The six most promising systems identified for next generation nuclear energy are described within the roadmap. Two employ a thermal neutron spectrum with coolants and temperatures that enable hydrogen or electricity production with high efficiency (the Supercritical Water Reactor - SCWR and the Very High Temperature Reactor - VHTR). Three employ a fast neutron spectrum to enable more effective management of actinides through recycling of most components in the discharged fuel (the Gas-cooled Fast Reactor - GFR, the Lead-cooled Fast Reactor - LFR, and the Sodium-cooled Fast Reactor - SFR). The Molten Salt Reactor (MSR) employs a circulating liquid fuel mixture that offers considerable flexibility for recycling actinides, and may provide an alternative to accelerator-driven systems. A few major technologies have been recognized by DOE as necessary to enable the deployment of the next generation of advanced nuclear reactors, including the development and qualification of the structural materials needed to ensure their safe and reliable operation. Accordingly, DOE has identified materials as one of the focus areas for Gen IV technology development.

  10. Light water reactor safety research program, quarterly report, July-September 1980. Volume 3

    SciTech Connect (OSTI)

    Berman, M.

    1981-04-01T23:59:59.000Z

    The report covers research performed during July-September 1980 for the NRC Light Water Reactor Safety Research Program comprised of: (1) The Molten Fuel Concrete Interactions (MFCI) study of experimental and analytical investigations of the chemical and physical phenomena associated with interactions between molten core materials and concrete; (2) Steam Explosion Phenomena program to assess the probability and consequences of steam explosions during postulated meltdown accidents in LWRs; (3) Separate Effects Tests for TRAP Code Development investigating vapor pressures of fission-product species at elevated temperatures, chemical compound formation and reaction rates; (4) Containment Emergency Sump Performance (CESP) program to investigate the reliability of ECCS sumps; (5) Hydrogen Program designed to quantify the threat posed by hydrogen released during LWR accidents; and (6) Combustible Gas in Containment Program to study the generation of H2 from the corrosion of zinc and other materials located within LWR containment buildings.

  11. Reactor safety research programs. Quarterly report, April-June 1983. Vol. 2

    SciTech Connect (OSTI)

    Edler, S.K. (ed.)

    1983-12-01T23:59:59.000Z

    This document summarizes work performed by Pacific Northwest Laboratory from April 1 through June 30, 1983, for the Division of Accident Evaluation and the Division of Engineering Technology, US Nuclear Regulatory Commission. Evaluations of nondestructive examination (NDE) techniques and instrumentation are reported; areas of investigation include demonstrating the feasibility of determining the strength of structural graphite, evaluating the feasibility of detecting and analyzing flaw growth in reactor pressure boundary systems, examining NDE reliability and probabilistic fracture mechanics, and assessing the integrity of pressurized water reactor steam generator tubes where service-induced degradation has been indicated. Experimental data and analytical models are being provided to aid in decision making regarding pipe-to-pipe impacts following postulated breaks in high-energy fluid system piping. Experimental data and validated models are being used to determine a method for evaluating the acceptance of welded or weld-repaired stainless steel piping. Core thermal models are being developed to provide better digital codes to compute the behavior or full-scale reactor systems under postulated accident conditions. High-temperature materials property tests are being conducted to provide data on severe core damage fuel behavior. Severe fuel damage accident tests are being conducted at the NRU reactor, Chalk River, Canada; and an instrumented fuel assembly irradiation program is being performed at Halden, Norway. Fuel assemblies and analytical support are being provided for experimental programs at other facilities, including fuel rod deformation and severe fuel damage tests for the Super Sara Test Program, Ispra, Italy; and experimental programs at the Power Burst Facility, Idaho National Engineering Laboratory, Idaho Falls, Idaho.

  12. CERCA LEU fuel assemblies testing in Maria Reactor - safety analysis summary and testing program scope.

    SciTech Connect (OSTI)

    Pytel, K.; Mieleszczenko, W.; Lechniak, J.; Moldysz, A.; Andrzejewski, K.; Kulikowska, T.; Marcinkowska, A.; Garner, P. L.; Hanan, N. A.; Nuclear Engineering Division; Institute of Atomic Energy (Poland)

    2010-03-01T23:59:59.000Z

    The presented paper contains neutronic and thermal-hydraulic (for steady and unsteady states) calculation results prepared to support annex to Safety Analysis Report for MARIA reactor in order to obtain approval for program of testing low-enriched uranium (LEU) lead test fuel assemblies (LTFA) manufactured by CERCA. This includes presentation of the limits and operational constraints to be in effect during the fuel testing investigations. Also, the scope of testing program (which began in August 2009), including additional measurements and monitoring procedures, is described.

  13. Light Water Reactor Safety Research Program. Semiannual report, October 1983-March 1984

    SciTech Connect (OSTI)

    Berman, M.

    1986-02-01T23:59:59.000Z

    This report describes the investigations and analyses conducted at Sandia National Laboratories, Albuquerque, in support of the Light Water Reactor Safety Research Program from October 1983 through March 1984. The Fuel-Coolant Interactions Study investigates the mechanism of concrete erosion by molten core materials, the nature and rate of generation of evolved gases, and the effects of fission-product release. The Hydrogen Behavior and Mitigative and Preventive Schemes Programs investigate the HECTR code for modeling hydrogen deflagration, and the Grand Gulf Igniter System II is being reviewed. All activities are continuing. 53 figs., 11 tabs.

  14. Advanced Gas Cooled Nuclear Reactor Materials Evaluation and Development Program. Progress report, January 1, 1980-March 31, 1980

    SciTech Connect (OSTI)

    Not Available

    1980-06-25T23:59:59.000Z

    Results are presented of work performed on the Advanced Gas-Cooled Nuclear Reactor Materials Evaluation and Development Program. The objectives of this program are to evaluate candidate alloys for Very High Temperature Reactor (VHTR) Nuclear Process Heat (NPH) and Direct Cycle Helium Turbine (DCHT) applications, in terms of the effect of simulated reactor primary coolant (helium containing small amounts of various other gases), high temperatures, and long time exposures, on the mechanical properties and structural and surface stability of selected candidate alloys. A second objective is to select and recommend materials for future test facilities and more extensive qualification programs. Included are the activities associated with the status of the simulated reactor helium supply system, testing equipment and gas chemistry analysis instrumentation and equipment. The progress in the screening test program is described, including screening creep results and metallographic analysis for materials thermally exposed or tested at 750, 850, and 950/sup 0/C.

  15. Designing Biological Systems for Sustainability and Programmed Environmental Interface (2011 JGI User Meeting)

    SciTech Connect (OSTI)

    Silver, Pam [Harvard University] [Harvard University

    2011-03-23T23:59:59.000Z

    The U.S. Department of Energy Joint Genome Institute (JGI) invited scientists interested in the application of genomics to bioenergy and environmental issues, as well as all current and prospective users and collaborators, to attend the annual DOE JGI Genomics of Energy & Environment Meeting held March 22-24, 2011 in Walnut Creek, Calif. The emphasis of this meeting was on the genomics of renewable energy strategies, carbon cycling, environmental gene discovery, and engineering of fuel-producing organisms. The meeting features presentations by leading scientists advancing these topics. Pam Silver of Harvard University gives a presentation on "Designing Biological Systems for Sustainability and Programmed Environmental Interface" at the 6th annual Genomics of Energy & Environment Meeting on March 23, 2011

  16. Designing Biological Systems for Sustainability and Programmed Environmental Interface (2011 JGI User Meeting)

    ScienceCinema (OSTI)

    Silver, Pam [Harvard University

    2011-06-03T23:59:59.000Z

    The U.S. Department of Energy Joint Genome Institute (JGI) invited scientists interested in the application of genomics to bioenergy and environmental issues, as well as all current and prospective users and collaborators, to attend the annual DOE JGI Genomics of Energy & Environment Meeting held March 22-24, 2011 in Walnut Creek, Calif. The emphasis of this meeting was on the genomics of renewable energy strategies, carbon cycling, environmental gene discovery, and engineering of fuel-producing organisms. The meeting features presentations by leading scientists advancing these topics. Pam Silver of Harvard University gives a presentation on "Designing Biological Systems for Sustainability and Programmed Environmental Interface" at the 6th annual Genomics of Energy & Environment Meeting on March 23, 2011

  17. China Energy Group - Sustainable Growth Through Energy Efficiency

    E-Print Network [OSTI]

    2006-01-01T23:59:59.000Z

    problems; the China Sustainable Energy Program (funded byFoundation's China Sustainable Energy Program commissionedFoundation (China Sustainable Energy Program) became major

  18. Reactor safety research programs. Quarterly report, October-December 1983. Vol. 4

    SciTech Connect (OSTI)

    Edler, S.K. (ed.)

    1984-05-01T23:59:59.000Z

    Evaluations of nondestructive examination (NDE) techniques and instrumentation include investigating the feasibility of detecting and analyzing flaw growth in reactor pressure boundary systems and examining NDE reliability and probabilistic fracture mechanics. Accelerated pellet-cladding interaction modeling is being conducted to predict the probability of fuel rod failure under normal operating conditions. Experimental data and analytical models are being provided to aid in decision making regarding pipe-to-pipe impacts following postulated breaks in high-energy fluid system piping. Experimental data and validated models are being used to determine a method for evaluating the acceptance of welded or weld-repaired stainless steel piping. Thermal-hydraulic models are being developed to provide better digital codes to compute the behavior of full-scale reactor systems under postulated accident conditions. High-temperature materials property tests are being conducted to provide data on severe core damage fuel behavior. Severe fuel damage accident tests are being conducted at the NRU reactor, Chalk River, Canada; an instrumented fuel assembly irradiation program is being performed at Halden, Norway; and fuel assemblies and analytical support are being provided for experimental programs at the Power Burst Facility.

  19. Interagency Sustainability Working Group: Update Report; December 2009, Federal Energy Management Program (FEMP) (Brochure)

    SciTech Connect (OSTI)

    Not Available

    2009-12-01T23:59:59.000Z

    December 2009 update report offered by the Interagency Sustainability Working Group (ISWG). This report is updated bi-annually.

  20. The RERTR (Reduced Enrichment Research and Test Reactor) Program: Progress and plans

    SciTech Connect (OSTI)

    Travelli, A.

    1987-01-01T23:59:59.000Z

    The progress of the Reduced Enrichment Research and Test Reactor (RERTR) Program is described. After a brief summary of the results which the RERTR Program, in collaboration with its many international partners, had achieved by the end of 1986, the activities, results, and new developments which occurred in 1987 are reviewed. Irradiation of the second miniplate series, concentrating on U/sub 3/Si/sub 2/-Al and U/sub 3/Si-Al fuels, was completed and postirradiation examinations were performed on many of its miniplates. The whole-core ORR demonstration with U/sub 3/Si/sub 2/-Al fuel at 4.8 g U/cm/sup 3/ was completed at the end of March with excellent results and with 29 elements estimated to have reached at least 40% average burnup. Good progress was made in the area of LEU usage for the production of fission /sup 99/Mo, and in the coordination of safety evaluations related to LEU conversions of US university reactors. Planned activities include testing and demonstrating advanced fuels intended to allow use of reduced enrichment uranium in very-high-performance reactors. Two candidate fuels are U/sub 3/Si-Al with 19.75% enrichment and U/sub 3/Si/sub 2/-Al with 45% enrichment. Demonstration of these fuels will include irradiation of full-size elements and, possibly, a full-core demonstration. Achievement of the final program goals is still projected for 1990. This progress could not have been possible without the close international cooperation which has existed from the beginning, and which is essential to the ultimate success of the RERTR Program.

  1. Office of Sustainability Support

    Broader source: Energy.gov [DOE]

    The Office of Sustainability Support serves as AU’s organizational lead in partnering with the Department’s Sustainability Performance Office to support the understanding and implementation of sustainability programs and requirements within the Department, including through supporting development and implementation of DOE’s annual Strategic Sustainability Program Plan.

  2. Light Water Reactor Sustainability Program Status Report on the Grizzly Code Enhancements

    SciTech Connect (OSTI)

    Stephen R. Novascone; Benjamin W. Spencer; Jason D. Hales

    2013-09-01T23:59:59.000Z

    This report summarizes work conducted during fiscal year 2013 to work toward developing a full capability to evaluate fracture contour J-integrals to the Grizzly code. This is a progress report on ongoing work. During the next fiscal year, this capability will be completed, and Grizzly will be capable of evaluating these contour integrals for 3D geometry, including the effects of thermal stress and large deformation. A usable, limited capability has been developed, which is capable of evaluating these integrals on 2D geometry, without considering the effects of material nonlinearity, thermal stress or large deformation. This report presents an overview of the approach used, along with a demonstration of the current capability in Grizzly, including a comparison with an analytical solution.

  3. Light Water Reactor Sustainability Program Power Uprate Research and Development Strategy

    SciTech Connect (OSTI)

    Hongbin Zhang

    2011-09-01T23:59:59.000Z

    The economic incentives for low-cost electricity generation will continue to drive more plant owners to identify safe and reliable methods to increase the electrical power output of the current nuclear power plant fleet. A power uprate enables a nuclear power plant to increase its electrical output with low cost. However, power uprates brought new challenges to plant owners and operators. These include equipment damage or degraded performance, and unanticipated responses to plant conditions, etc. These problems have arisen mainly from using dated design and safety analysis tools and insufficient understanding of the full implications of the proposed power uprate or from insufficient attention to detail during the design and implementation phase. It is essential to demonstrate that all required safety margins have been properly retained and the existing safety level has been maintained or even increased, with consideration of all the conditions and parameters that have an influence on plant safety. The impact of the power uprate on plant life management for long term operation is also an important issue. Significant capital investments are required to extend the lifetime of an aging nuclear power plant. Power uprates can help the plant owner to recover the investment costs. However, plant aging issues may be aggravated by the power uprate due to plant conditions. More rigorous analyses, inspections and monitoring systems are required.

  4. INL/EXT-14-33251 Light Water Reactor Sustainability Program

    Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

    in Grizzly span these scales, as described below. At the engineering scale, 3D fracture mechanics capabilities have been developed to calculate stress intensities and...

  5. INL/EXT-14-33186 Light Water Reactor Sustainability Program

    Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

    Advanced Safety Analysis Project Plan FY 2015 - FY 2019 Ronaldo H Szilard Curtis L Smith Robert Youngblood September 2014 DOE Office of Nuclear Energy DISCLAIMER This...

  6. Light Water Reactor Sustainability (LWRS) Program - R&D Roadmap for

    Energy Savers [EERE]

    AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative Fuels Data Center Home Page on Google Bookmark EERE: Alternative Fuels Data Center Home Page on Office of Inspector General Office0-72.pdfGeorgeDoesn't Happen toLeveraging National Laboratories

  7. Light-water-reactor safety research program. Quarterly progress report, July-September 1980

    SciTech Connect (OSTI)

    Massey, W.E.; Till, C.E.

    1981-02-01T23:59:59.000Z

    A physically realistic description of fuel swelling and fission-gas release is needed to aid in predicting the behavior of fuel rods and fission gases under certain hypothetical light-water-reactor (LWR) accident conditions. To satisfy this need, a comprehensive computer-base model, the Steady-State and Transient Gas-Release and Swelling Subroutine (GRASS-SST), its faster-running version, FASTGRASS, and correlations based on analyses performed with GRASS-SST, PARAGRASS, are being developed at Argonne National Laboratory (ANL). This model is being incorporated into the Fuel-Rod Analysis Program (FRAP) code being developed by EG and G Idaho, Inc., at the Idaho National Engineering Laboratory (INEL). The analytical effort is supported by a data base and correlations developed from characterization of irradiated LWR fuel and from out-of-reactor transient heating tests of irradiated commercial and experimental LWR fuel under a range of thermal conditions. 7 refs., 2 figs.

  8. Reactor safety research programs. Quarterly report, October-December 1984. Volume 4

    SciTech Connect (OSTI)

    Edler, S.K. (ed.)

    1985-05-01T23:59:59.000Z

    Results from an instrumented fuel assembly irradiation program being performed at Halden, Norway, are reported. Accelerated pellet-cladding interaction modeling is being conducted to predict the probability of fuel rod failure under normal operating conditions. Experimental data and analytical models are being provided to aid in decision making regarding pipe-to-pipe impacts following postulated breaks in high-energy fluid system piping. Fuel assemblies and analytical support are being provided for experimental programs at the Power Burst Facility, Idaho National Engineering Laboratory, Idaho Falls, Idaho. High-temperature materials property tests are being conducted to provide data on severe core damage fuel behavior. Thermal-hydraulic computer programs are providing best-estimate analyses for a variety of safety issues in light-water reactors. 8 figs., 1 tab.

  9. SRS Small Modular Reactors

    SciTech Connect (OSTI)

    None

    2012-04-27T23:59:59.000Z

    The small modular reactor program at the Savannah River Site and the Savannah River National Laboratory.

  10. SRS Small Modular Reactors

    ScienceCinema (OSTI)

    None

    2014-05-21T23:59:59.000Z

    The small modular reactor program at the Savannah River Site and the Savannah River National Laboratory.

  11. Participation in the United States Department of Energy Reactor Sharing Program. Final report, September 1980--August 1992

    SciTech Connect (OSTI)

    Mulder, R.U.; Benneche, P.E.; Hosticka, B.

    1992-12-01T23:59:59.000Z

    The University of Virginia Reactor Facility is an integral part of the Department of Mechanical, Aerospace and Nuclear Engineering and is used to support educational programs in engineering and science at the University of Virginia and at other area colleges and universities. The University of Virginia Research Reactor (UVAR) is the highest power (two megawatts thermal power) and one of the most utilized university research reactor in the mid-Atlantic states. A major objective of this facility is to support educational programs in the region. The University of Virginia has received support under the US Department of Energy (DOE) Reactor Sharing Program every year since 1978 to assist in meeting this objective. This report documents the major educational accomplishments under the Reactor Sharing Program for the period September 1991 through August 1992. This report is also to final report under this contract. Previous annual reports should be consulted if any information from those periods is desired. Additional information about the programs conducted at UVA under this contract may be found in the yearly requests for additional funds which have been submitted.

  12. Nuclear Systems Enhanced Performance Program, Maintenance Cycle Extension in Advanced Light Water Reactor Design

    SciTech Connect (OSTI)

    Professor Neill Todreas

    2001-10-01T23:59:59.000Z

    A renewed interest in new nuclear power generation in the US has spurred interest in developing advanced reactors with features which will address the public's concerns regarding nuclear generation. However, it is economic performance which will dictate whether any new orders for these plants will materialize. Economic performance is, to a great extent, improved by maximizing the time that the plant is on-line generating electricity relative to the time spent off-line conducting maintenance and refueling. Indeed, the strategy for the advanced light water reactor plant IRIS (International Reactor, Innovative and Secure) is to utilize an eight year operating cycle. This report describes a formalized strategy to address, during the design phase, the maintenance-related barriers to an extended operating cycle. The top-level objective of this investigation was to develop a methodology for injecting component and system maintainability issues into the reactor plant design process to overcome these barriers. A primary goal was to demonstrate the applicability and utility of the methodology in the context of the IRIS design. The first step in meeting the top-level objective was to determine the types of operating cycle length barriers that the IRIS design team is likely to face. Evaluation of previously identified regulatory and investment protection surveillance program barriers preventing a candidate operating PWR from achieving an extended (48 month) cycle was conducted in the context of the IRIS design. From this analysis, 54 known IRIS operating cycle length barriers were identified. The resolution methodology was applied to each of these barriers to generate design solution alternatives for consideration in the IRIS design. The methodology developed has been demonstrated to narrow the design space to feasible design solutions which enable a desired operating cycle length, yet is general enough to have broad applicability. Feedback from the IRIS design team indicates that the proposed solutions to the investigated operating cycle length barriers are both feasible and consistent with sound design practice.

  13. Boiling water reactor control rod programming using heuristic and mathematical methods

    SciTech Connect (OSTI)

    Hayase, T.; Motoda, H.

    1980-04-01T23:59:59.000Z

    OPROD, a computer code for automatic generation of control rod programming that has successfully been applied to an older boiling water reactor (BWR), has experienced some difficulties when applied to a BWR of larger power density and stronger heterogeneity. To improve the performance, a heuristic algorithm that is derived from accumulated experience has been introduced to search for a feasible rod pattern that satisfies all constraints. Application of this algorithm to an initial cycle of an 800-MW(e) BWR of high heterogeneity has been very successful. It has been demonstrated that the proposed algorithm is capable of finding a feasible rod pattern, even starting from an all-rods-out pattern. Some improvement was also made in the method of approximation programming (MAP) algorithm. The temporal constraint relaxation method is shown to be effective in finding an optimal control rod pattern in MAP starting from a guess pattern that is not feasible.

  14. Reactor Safety Research Programs. Quarterly report, July-September 1984. Volume 3. [PWR; BWR

    SciTech Connect (OSTI)

    Edler, S.K. (ed.)

    1985-02-01T23:59:59.000Z

    This document summarizes work performed by Pacific Northwest Laboratory from July 1 through September 30, 1984, for the Division of Accident Evaluation and the Division of Engineering Technology, US Nuclear Regulatory Commission. Results from an instrumented fuel assembly irradiation program being performed at Halden, Norway, are reported. Accelerated pellet-cladding interaction modeling is being conducted to predict the probability of fuel rod failure under normal operating conditions. Experimental data and analytical models are being provided to aid in decision making regarding pipe-to-pipe impacts following postulated breaks in high-energy fluid system piping. Fuel assemblies and analytical support are being provided for experimental programs at the Power Burst Facility, Idaho National Engineering Laboratory, Idaho Falls, Idaho. High-temperature materials property tests are being conducted to provide data on severe core damage fuel behavior. Thermal-hydraulic models are being developed to provide better digital codes to compute the behavior of full-scale reactor systems under postulated accident conditions. Severe fuel damage accident tests are being conducted in the NRU Reactor, Chalk River, Canada.

  15. Reactor safety research programs. Quarterly report, January-March 1984. Vol. 1. [PWR; BWR

    SciTech Connect (OSTI)

    Edler, S.K. (ed.)

    1984-06-01T23:59:59.000Z

    This document summarizes work performed by Pacific Northwest Laboratory from January 1 through March 31, 1984, for the Division of Accident Evaluation and the Division of Engineering Technology, US Nuclear Regulatory Commission. Results from an instrumented fuel assembly irradiation program being performed at Halden, Norway, are reported. Accelerated pellet-cladding interaction modeling is being conducted to predict the probability of fuel rod failure under normal operating conditions. Experimental data on analytical models are being provided to aid in decision making regarding pipe-to-pipe impacts following postulated breaks in high-energy fluid system piping. Fuel assemblies and analytical support are being provided for experimental programs at the Power Burst Facility, Idaho National Engineering Laboratory, Idaho Falls, Idaho. High-temperature materials property tests are being conducted to provide data on severe core damage fuel behavior. Thermal-hydraulic models are being developed to provide better digital codes to compute the behavior of full-scale reactor systems under postulated accident conditions. Severe fuel damage accident tests are being conducted at the NRU reactor, Chalk River, Canada.

  16. Reactor safety research programs. Quarterly report, April-June 1984. Volume 2

    SciTech Connect (OSTI)

    Edler, S.K. (ed.)

    1984-11-01T23:59:59.000Z

    This document summarizes work performed by Pacific Northwest Laboratory from April 1 through June 30, 1984, for the Division of Accident Evaluation and the Division of Engineering Technology, US Nuclear Regulatory Commission. Results from an instrumented fuel assembly irradiation program being performed at Halden, Norway, are reported. Accelerated pellet-cladding interaction modeling is being conducted to predict the probability of fuel rod failure under normal operating conditions. Experimental data and analytical models are being provided to aid in decision making regarding pipe-to-pipe impacts following postulated breaks in high-energy fluid system piping. Fuel assemblies and analytical support are being provided for experimental programs at the Power Burst Facility, Idaho National Engineering Laboratory, Idaho Falls, Idaho. High-temperature materials property tests are being conducted to provide data on severe core damage fuel behavior. Thermal-hydraulic models are being developed to provide better digital codes to compute the behavior of full-scale reactor systems under postulated accident conditions. Severe fuel damage accident tests are being conducted at the NRU reactor, Chalk River, Canada.

  17. Status of the RERTR (Reduced Enrichment Research and Test Reactor) Program

    SciTech Connect (OSTI)

    Travelli, A.

    1988-01-01T23:59:59.000Z

    The progress of the Reduced Enrichment Research and Test Reactor (RERTR) Program is described. After a brief summary of the results which the RERTR Program, in collaboration with its many international partners, had achieved by the end of 1987, the major events, findings and activities of 1988 are reviewed. The US Nuclear Regulatory Commission issued a formal and generic approval of the use of U3Si2-Al dispersion fuel in research and test reactors, with densities up to 4.8 g U/cmT. New significant findings from postirradiation examinations, from ion-beam irradiations, and from analytical modeling, have raised serious doubts about the potential of LEU U3Si-Al dispersion fuel for applications requiring very high uranium densities and high burnups (>6 g U/cmT, >50% burnup). As a result of these findings, the fuel development efforts have been redirected towards three new initiatives: (1) a systematic application of ion-beam irradiations to screen new materials; (2) application of Hot Isostatic Pressing (HIP) procedures to produce U3Si2-Al plates with high uranium densities and thin uniform cladding; and (3) application of HIP procedures to produce plates with U3Si wires imbedded in an aluminum matrix, achieving stability, high uranium density, and thin uniform cladding. The new fuel concepts hold the promise of extraordinary performance potential and require approximately five years to develop.

  18. DOE-NE Light Water Reactor Sustainability Program and EPRI Long-Term Operations Program – Joint Research and Development Plan

    SciTech Connect (OSTI)

    Don Williams

    2012-04-01T23:59:59.000Z

    Nuclear power has contributed almost 20% of the total amount of electricity generated in the United States over the past two decades. High capacity factors and low operating costs make nuclear power plants (NPPs) some of the most economical power generators available. Further, nuclear power remains the single largest contributor (nearly 70%) of non-greenhouse gas-emitting electric power generation in the United States. Even when major refurbishments are performed to extend operating life, these plants continue to represent cost-effective, low-carbon assets to the nation's electrical generation capability.

  19. DOE-NE Light Water Reactor Sustainability Program and EPRI Long-Term Operations Program – Joint Research and Development Plan

    SciTech Connect (OSTI)

    Don Williams

    2014-04-01T23:59:59.000Z

    Nuclear power has contributed almost 20% of the total amount of electricity generated in the United States over the past two decades. High capacity factors and low operating costs make nuclear power plants (NPPs) some of the most economical power generators available. Further, nuclear power remains the single largest contributor (nearly 70%) of non-greenhouse gas-emitting electric power generation in the United States. Even when major refurbishments are performed to extend operating life, these plants continue to represent cost-effective, low-carbon assets to the nation’s electrical generation capability.

  20. DOE-NE Light Water Reactor Sustainability Program and EPRI Long Term Operation Program - Joint Research & Development Plan

    Broader source: Energy.gov (indexed) [DOE]

    AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE:1 First Use of Energy for All Purposes (Fuel and Nonfuel),Feet) Year Jan Feb Mar Apr May Jun Jul(Summary) "ofEarly Career Scientists'Montana. DOCUMENTSofDATE M a y 9, 2005 REPLY TO530-98viii4-97 SENSITIVEL.__2-24562

  1. AURORA: A FORTRAN program for modeling well stirred plasma and thermal reactors with gas and surface reactions

    SciTech Connect (OSTI)

    Meeks, E.; Grcar, J.F.; Kee, R.J. [Sandia National Labs., Livermore, CA (United States). Thermal and Plasma Processes Dept.] [Sandia National Labs., Livermore, CA (United States). Thermal and Plasma Processes Dept.; Moffat, H.K. [Sandia National Labs., Albuquerque, NM (United States). Surface Processing Sciences Dept.] [Sandia National Labs., Albuquerque, NM (United States). Surface Processing Sciences Dept.

    1996-02-01T23:59:59.000Z

    The AURORA Software is a FORTRAN computer program that predicts the steady-state or time-averaged properties of a well mixed or perfectly stirred reactor for plasma or thermal chemistry systems. The software was based on the previously released software, SURFACE PSR which was written for application to thermal CVD reactor systems. AURORA allows modeling of non-thermal, plasma reactors with the determination of ion and electron concentrations and the electron temperature, in addition to the neutral radical species concentrations. Well stirred reactors are characterized by a reactor volume, residence time or mass flow rate, heat loss or gas temperature, surface area, surface temperature, the incoming temperature and mixture composition, as well as the power deposited into the plasma for non-thermal systems. The model described here accounts for finite-rate elementary chemical reactions both in the gas phase and on the surface. The governing equations are a system of nonlinear algebraic relations. The program solves these equations using a hybrid Newton/time-integration method embodied by the software package TWOPNT. The program runs in conjunction with the new CHEMKIN-III and SURFACE CHEMKIN-III packages, which handle the chemical reaction mechanisms for thermal and non-thermal systems. CHEMKIN-III allows for specification of electron-impact reactions, excitation losses, and elastic-collision losses for electrons.

  2. Consolidated fuel reprocessing program: Criticality experiments with fast test reactor fuel pins in an organic moderator

    SciTech Connect (OSTI)

    Bierman, S.R.

    1986-12-01T23:59:59.000Z

    The results obtained in a series of criticality experiments performed as part of a joint program on criticality data development between the United States Department of Energy and the Power Reactor and Nuclear Fuel Development Corporation of Japan are presented in this report along with a complete description of the experiments. The experiments involved lattices of Fast Test Reactor (FTR) fuel pins in an organic moderator mixture similar to that used in the solvent extraction stage of fuel reprocessing. The experiments are designed to provide data for direct comparison with previously performed experimental measurements with water moderated lattices of FTR fuel pins. The same lattice arrangements and FTR fuel pin types are used in these organic moderated experimental assemblies as were used in the water moderated experiments. The organic moderator is a mixture of 38 wt % tributylphosphate in a normal paraffin hydrocarbon mixture of C{sub 11}H{sub 24} to C{sub 15}H{sub 32} molecules. Critical sizes of 1054.8, 599.2, 301.8, 199.5 and 165.3 fuel pins were obtained respectively for organic moderated lattices having 0.761 cm, 0.968 cm, 1.242 cm, 1.537 cm and 1.935 cm square lattice pitches as compared to 1046.9, 571.9, 293.9, 199.7 and 165.1 fuel pins for the same lattices water moderated.

  3. Promoting safety, security, and sustainability: Institute fosters programs on natural resource science and management

    E-Print Network [OSTI]

    Wythe, Kathy

    2011-01-01T23:59:59.000Z

    science and management, the Texas A&M Institute of Renewable Natural Resources (IRNR) protects and promotes the safety, security, and sustainability of land, water, and wildlife. IRNR, a unit of Texas AgriLife Research and the Texas Agri... projects that promote sustainable land use through stewardship practices, land-use forecasting and policy, restoration ecology, and ecosystem services. Involved in working on landscape-scale restoration projects, IRNR developed the Trinity River...

  4. Participation in the United States Department of Energy Reactor Sharing Program. Annual report, August 31, 1991--August 29, 1992

    SciTech Connect (OSTI)

    Mulder, R.U.; Benneche, P.E.; Hosticka, B.

    1992-05-01T23:59:59.000Z

    The University of Virginia Reactor Facility is an integral part of the Department of Nuclear Engineering and Engineering Physics (to become the Department of Mechanical, Aerospace and Nuclear Engineering on July 1, 1992). As such, it is effectively used to support educational programs in engineering and science at the University of Virginia as well as those at other area colleges and universities. The expansion of support to educational programs in the mid-east region is a major objective. To assist in meeting this objective, the University of Virginia has been supported under the US Department of Energy (DOE) Reactor Sharing Program since 1978. Due to the success of the program, this proposal requests continued DOE support through August 1993.

  5. WINTER 2014 Sustainability and

    E-Print Network [OSTI]

    Stephens, Graeme L.

    WINTER 2014 Sustainability and Renewable Energy in Costa Rica January 4 - 14 Dr. James Hoffmann, Program Director Lecturer Sustainability Studies Program E-511 Melville Library Stony Brook, NY 11794 sustainability and renewable energy. Students will spend 11 days in Costa Rica to participate in site visits

  6. Results from the DOE Advanced Gas Reactor Fuel Development and Qualification Program

    SciTech Connect (OSTI)

    David Petti

    2014-06-01T23:59:59.000Z

    Modular HTGR designs were developed to provide natural safety, which prevents core damage under all design basis accidents and presently envisioned severe accidents. The principle that guides their design concepts is to passively maintain core temperatures below fission product release thresholds under all accident scenarios. This level of fuel performance and fission product retention reduces the radioactive source term by many orders of magnitude and allows potential elimination of the need for evacuation and sheltering beyond a small exclusion area. This level, however, is predicated on exceptionally high fuel fabrication quality and performance under normal operation and accident conditions. Germany produced and demonstrated high quality fuel for their pebble bed HTGRs in the 1980s, but no U.S. manufactured fuel had exhibited equivalent performance prior to the Advanced Gas Reactor (AGR) Fuel Development and Qualification Program. The design goal of the modular HTGRs is to allow elimination of an exclusion zone and an emergency planning zone outside the plant boundary fence, typically interpreted as being about 400 meters from the reactor. To achieve this, the reactor design concepts require a level of fuel integrity that is better than that claimed for all prior US manufactured TRISO fuel, by a few orders of magnitude. The improved performance level is about a factor of three better than qualified for German TRISO fuel in the 1980’s. At the start of the AGR program, without a reactor design concept selected, the AGR fuel program selected to qualify fuel to an operating envelope that would bound both pebble bed and prismatic options. This resulted in needing a fuel form that could survive at peak fuel temperatures of 1250°C on a time-averaged basis and high burnups in the range of 150 to 200 GWd/MTHM (metric tons of heavy metal) or 16.4 to 21.8% fissions per initial metal atom (FIMA). Although Germany has demonstrated excellent performance of TRISO-coated UO2 particle fuel up to about 10% FIMA and 1150°C, UO2 fuel is known to have limitations because of CO formation and kernel migration at the high burnups, power densities, temperatures, and temperature gradients that may be encountered in the prismatic modular HTGRs. With uranium oxycarbide (UCO) fuel, the kernel composition is engineered to prevent CO formation and kernel migration, which are key threats to fuel integrity at higher burnups, temperatures, and temperature gradients. Furthermore, the recent poor fuel performance of UO2 TRISO fuel pebbles measured in Chinese irradiation testing in Russia and in German pebbles irradiated at 1250°C, and historic data on poorer fuel performance in safety testing of German pebbles that experienced burnups in excess of 10% FIMA [1] have each raised concern about the use of UO2 TRISO above 10% FIMA and 1150°C and the degree of margin available in the fuel system. This continues to be an active area of study internationally.

  7. Status of the RERTR program: overview, progress and plans. [Reduced Enrighment Research and Test Reactor

    SciTech Connect (OSTI)

    Travelli, A.

    1985-01-01T23:59:59.000Z

    The status of the US Reduced Enrichment Research and Test Reactor (RERTR) Program is reviewed. After a summary of the accomplishments which the RERTR Program had achieved by the end of 1984 with its many international partners, emphasis is placed on the progress achieved during 1985 and on current plans and schedules. A new miniplate series, concentrating on U/sub 3/Si/sub 2/-Al and U/sub 3/Si-Al fuels, was fabricated and is well into irradiation. The whole-core ORR demonstration is scheduled to begin in November 1985, with U/sub 3/Si/sub 2/-Al fuel at 4.8 g U/cm/sup 3/. Altogether, 921 full-size test and prototype elements have been ordered for fabrication with reduced enrichment and the new technologies. Qualification of U/sub 3/Si-Al fuel with approx.7 g U/cm/sup 3/ is still projected for 1989. This progress could not have been achieved without the close international cooperation which has existed since the beginning, and whose continuation and intensification will be essential to the achievement of the long-term RERTR goals.

  8. U.S. Department Of Energy Advanced Small Modular Reactor R&D Program: Instrumentation, Controls, and Human-Machine Interface (ICHMI) Pathway

    SciTech Connect (OSTI)

    Holcomb, David Eugene [ORNL; Wood, Richard Thomas [ORNL

    2013-01-01T23:59:59.000Z

    Instrumentation, controls, and human-machine interfaces (ICHMI) are essential enabling technologies that strongly influence nuclear power plant performance and operational costs. The nuclear power industry is currently engaged in a transition from traditional analog-based instrumentation, controls, and human-machine interface systems to implementations employing digital technologies. This transition has primarily occurred in an ad hoc fashion through individual system upgrades at existing plants and has been constrained by licenseability concerns. Although the recent progress in constructing new plants has spurred design of more fully digital plant-wide ICHMI systems, the experience base in the nuclear power application domain is limited. Additionally, development of advanced reactor concepts, such as Generation IV designs and small modular reactors, introduces different plant conditions (e.g., higher temperatures, different coolants, etc.) and unique plant configurations (e.g., multiunit plants with shared systems, balance of plant architectures with reconfigurable co-generation options) that increase the need for enhanced ICHMI capabilities to fully achieve industry goals related to economic competitiveness, safety and reliability, sustainability, and proliferation resistance and physical protection. As a result, significant challenges remain to be addressed to enable the nuclear power industry to complete the transition to safe and comprehensive use of modern ICHMI technology. The U.S. Department of Energy (DOE) has recognized that ICHMI research, development, and demonstration (RD&D) is needed to resolve the technical challenges that may compromise the effective and efficient utilization of modern ICHMI technology and consequently inhibit realization of the benefits offered by expanded utilization of nuclear power. Consequently, several DOE programs have substantial ICHMI RD&D elements within their respective research portfolios. This paper describes current ICHMI research in support of advanced small modular reactors. The objectives that can be achieved through execution of the defined RD&D are to provide optimal technical solutions to critical ICHMI issues, resolve technology gaps arising from the unique measurement and control characteristics of advanced reactor concepts, provide demonstration of needed technologies and methodologies in the nuclear power application domain, mature emerging technologies to facilitate commercialization, and establish necessary technical evidence and application experience to enable timely and predictable licensing. 1 Introduction Instrumentation, controls, and human-machine interfaces are essential enabling technologies that strongly influence nuclear power plant performance and operational costs. The nuclear power industry is currently engaged in a transition from traditional analog-based instrumentation, controls, and human-machine interface (ICHMI) systems to implementations employing digital technologies. This transition has primarily occurred in an ad hoc fashion through individual system upgrades at existing plants and has been constrained by licenseability concerns. Although the recent progress in constructing new plants has spurred design of more fully digital plant-wide ICHMI systems, the experience base in the nuclear power application domain is limited. Additionally, development of advanced reactor concepts, such as Generation IV designs and small modular reactors, introduces different plant conditions (e.g., higher temperatures, different coolants, etc.) and unique plant configurations (e.g., multiunit plants with shared systems, balance of plant architectures with reconfigurable co-generation options) that increase the need for enhanced ICHMI capabilities to fully achieve industry goals related to economic competitiveness, safety and reliability, sustainability, and proliferation resistance and physical protection. As a result, significant challenges remain to be addressed to enable the nuclear power industry to complete the transition to safe and comprehensive use of m

  9. Neutron behavior, reactor control, and reactor heat transfer. Volume four

    SciTech Connect (OSTI)

    Not Available

    1986-01-01T23:59:59.000Z

    Volume four covers neutron behavior (neutron absorption, how big are nuclei, neutron slowing down, neutron losses, the self-sustaining reactor), reactor control (what is controlled in a reactor, controlling neutron population, is it easy to control a reactor, range of reactor control, what happens when the fuel burns up, controlling a PWR, controlling a BWR, inherent safety of reactors), and reactor heat transfer (heat generation in a nuclear reactor, how is heat removed from a reactor core, heat transfer rate, heat transfer properties of the reactor coolant).

  10. Sustainable distributed biodiesel manufacturing under uncertainty: An interval-parameter-programming-based approach

    E-Print Network [OSTI]

    Huang, Yinlun

    Sustainable distributed biodiesel manufacturing under uncertainty: An interval A sophisticated biodiesel manufacturing study demonstrated methodological efficacy. a r t i c l e i n f o Article Simulation Uncertainty a b s t r a c t Biodiesel, a clean-burning alternative fuel, can be produced using

  11. Environmental Sustainability & Green Energy

    E-Print Network [OSTI]

    Denham, Graham

    of carbon nanotubes for solar energy ¡ ChemicalReactorEngineeringCentre: developing innovative green reactorEnvironmental Sustainability & Green Energy With escalating concerns about global energy shortages technologies and discovering alternative sources of energy. Western University has emerged as a leader

  12. Gas-cooled reactor programs: high-temperature gas-cooled reactor technology development program. Annual progress report for period ending December 31, 1981

    SciTech Connect (OSTI)

    Not Available

    1982-06-01T23:59:59.000Z

    Information is presented concerning HTGR chemistry; fueled graphite development; irradiation services for General Atomic Company; prestressed concrete pressure vessel development; HTGR structural materials; graphite development; high-temperature reactor physics studies; shielding studies; component flow test loop studies; core support performance test; and application and project assessments.

  13. Former Tribal Energy Program Intern Guides Tribes Toward a More Sustainable Path

    Broader source: Energy.gov [DOE]

    Suzanne Singer is working at the Lawrence Livermore National Laboratory (LLNL) as an Energy and Thermal Fluids Analyst where she has an ongoing project to produce Sankey diagrams to analyze energy data and life cycle flows on tribal lands. Applying the knowledge and insights she gained from her work at LLNL, her internship, and her science, technology, engineering, and math (STEM) education, Singer is educating Tribes on how to use their own resources and land to live a more sustainable lifestyle.

  14. Catalytic membrane program novation: High temperature catalytic membrane reactors. Final report

    SciTech Connect (OSTI)

    Kleiner, R.N. [Kleiner (Richard N.), Englewood, CO (United States)] [Kleiner (Richard N.), Englewood, CO (United States)

    1998-08-28T23:59:59.000Z

    The original objective was to develop an energy-efficient hydrocarbon dehydrogenation process based on catalytic membrane reactors. Golden Technologies determined that the goals of this contract would be best served by novating the contract to an end user or other interested party which is better informed on the economic justification aspects of petrochemical refining processes to carry out the remaining work. In light of the Chevron results, the program objective was broadened to include development of inorganic membranes for applications in the chemical industry. The proposed membrane technologies shall offer the potential to improve chemical production processes via conversion increase and energy savings. The objective of this subcontract is to seek a party that would serve as a prime contractor to carry out the remaining tasks on the agreement and bring the agreement to a successful conclusion. Four tasks were defined to select the prime contractor. They were (1) prepare a request for proposal, (2) solicit companies as potential prime contractors as well as team members, (3) discuss modifications requested by the potential prime contractors, and (4) obtain, review and rank the proposals. The accomplishments on the tasks is described in detail in the following sections.

  15. Plutonium Consumption Program, CANDU Reactor Project: Feasibility of BNFP Site as MOX Fuel Supply Facility. Final report

    SciTech Connect (OSTI)

    NONE

    1995-06-30T23:59:59.000Z

    An evaluation was made of the technical feasibility, cost, and schedule for converting the existing unused Barnwell Nuclear Fuel Facility (BNFP) into a Mixed Oxide (MOX) CANDU fuel fabrication plant for disposition of excess weapons plutonium. This MOX fuel would be transported to Ontario where it would generate electricity in the Bruce CANDU reactors. Because CANDU MOX fuel operates at lower thermal load than natural uranium fuel, the MOX program can be licensed by AECB within 4.5 years, and actual Pu disposition in the Bruce reactors can begin in 2001. Ontario Hydro will have to be involved in the entire program. Cost is compared between BNFP and FMEF at Hanford for converting to a CANDU MOX facility.

  16. Light-water-reactor safety research program. Quarterly progress report, July to September 1981

    SciTech Connect (OSTI)

    Not Available

    1982-02-01T23:59:59.000Z

    Information is presented concerning environmentally assisted cracking in light water reactors; transient fuel response and fission-product release; and clad properties for code verification.

  17. Light Water Reactor Sustainability (LWRS) Initiative Science-Based R&D to Extend Nuclear Plant Operation

    Broader source: Energy.gov (indexed) [DOE]

    AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE:1 First Use of Energy for All Purposes (Fuel and Nonfuel),Feet) Year Jan Feb Mar Apr May Jun Jul(Summary) "ofEarly Career Scientists'Montana.ProgramJulietipDepartmentJuneWhenJuly 28,The U.S. Life CyclePowerA LED

  18. Sustainable Development Report

    E-Print Network [OSTI]

    Laval, Université

    Sustainable Development Report 2010-2011 #12;2 Table of Contents Université Laval at a glance 2-2011 highlights 9 University community initiatives 15 Sustainable development educational program 21 Research and creativity in sustainable development 24 Awards, recognition, and distinctions 28 Implementation

  19. Our program is immersed in a culture of sustainability at Appalachian

    E-Print Network [OSTI]

    Thaxton, Christopher S.

    -Focused Majors/Programs BS, MS in Appropriate Technology BS, MS in Building Science BS in Environmental Science w/Lab Environmental Chemistry Biology Systematic Botany Marine Sciences Air Pollution Effects Environmental Science program Chancellor Kenneth Peacock joins 677 colleges and universities in signing

  20. Analysis of a research reactor under anticipated transients without scram events using the RELAP5/MOD3.2 computer program

    E-Print Network [OSTI]

    Hari, Sridhar

    1998-01-01T23:59:59.000Z

    Simulations for two series of anticipated transients phics. without scram (ATWS) events have been carried out for a small, hypothetical, research reactor based on the High Flux Australian Reador HIFAR using the RELAPS/MOD3.Z computer program...

  1. October 30, 2008, Visiting Speakers Program - Dow Chemicals Presentation - Dows Approach to Sustainability

    Office of Environmental Management (EM)

    AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE:1 First Use of Energy for All Purposes (Fuel and Nonfuel),Feet) Year Jan Feb Mar Apr May Jun Jul(Summary) "of EnergyEnergyENERGY TAXBalanced ScorecardReactor TechnologyOFFICE: I Oak Ridge,8October 2013Catalyst for

  2. Materials science division light-water-reactor safety research program. Quarterly progress report, October - December 1981

    SciTech Connect (OSTI)

    Not Available

    1982-05-01T23:59:59.000Z

    This progress report summarizes the Argonne National Laboratory work performed during October, November, and December 1981 on water-reactor-safety problems. The research and development areas covered are environmentally assisted cracking in light water reactors, transient fuel response and fission-product release, and clad properties for code verification.

  3. Light-water-reactor safety research program. Quarterly progress report, April-June 1981

    SciTech Connect (OSTI)

    Not Available

    1981-01-01T23:59:59.000Z

    This progress report summarizes the Argonne National Laboratory work performed during April, May, and June 1981 on water-reactor-safety problems. The research and development areas covered are transient fuel response and fission-product release and environmentally assisted cracking in light water reactors.

  4. Cognitive objectives vs Affective objectives in Sustainability curriculum In exploring for the general goals of an academic program in sustainability, even if only

    E-Print Network [OSTI]

    Zaferatos, Nicholas C.

    Cognitive objectives vs Affective objectives in Sustainability curriculum In exploring to follow Bloom's distinction between cognitive objectives and affective objectives: Remember: Demonstrate goals, while England chooses language to emphasize cognitive learning goals. Australia: Understand

  5. Light-water-reactor safety research program. Quarterly progress report, January-March 1980

    SciTech Connect (OSTI)

    Massey, W.E.; Kyger, J.A.

    1980-08-01T23:59:59.000Z

    This progress report summarizes the Argonne National Laboratory work performed during January, February, and March 1980 on water-reactor-safety problems. The research and development area covered is Transient Fuel Response and Fission-Product Release.

  6. Light-water-reactor safety research program: quarterly progress report, July-September, 1980

    SciTech Connect (OSTI)

    Massey, W.E.; Till, C.E.

    1981-04-01T23:59:59.000Z

    The progress report summarizes the Argonne National Laboratory work performed during July, August, and September 1980 on water-reactor-safety problems. The research and development area covered is Transient Fuel Response and Fission-product Release.

  7. Process Modeling Phase I Summary Report for the Advanced Gas Reactor Fuel Development and Qualification Program

    SciTech Connect (OSTI)

    Pannala, Sreekanth [ORNL; Daw, C Stuart [ORNL; Boyalakuntla, Dhanunjay S [ORNL; FINNEY, Charles E A [ORNL

    2006-09-01T23:59:59.000Z

    This report summarizes the results of preliminary work at Oak Ridge National Laboratory (ORNL) to demonstrate application of computational fluid dynamics modeling to the scale-up of a Fluidized Bed Chemical Vapor Deposition (FBCVD) process for nuclear fuels coating. Specifically, this work, referred to as Modeling Scale-Up Phase I, was conducted between January 1, 2006 and March 31, 2006 in support of the Advanced Gas Reactor (AGR) Program. The objective was to develop, demonstrate and "freeze" a version of ORNL's computational model of the TRI ISOtropic (TRISO) fuel-particle coating process that can be specifically used to assist coater scale-up activities as part of the production of AGR-2 fuel. The results in this report are intended to serve as input for making decisions about initiating additional FBCVD modeling work (referred to as Modeling Scale-Up Phase II) in support of AGR-2. The main computational tool used to implement the model is the general-purpose multiphase fluid-dynamics computer code known as MFIX (Multiphase Flow with Interphase eXchanges), which is documented in detail on the DOE-sponsored website http://www.mfix.org. Additional computational tools are also being developed by ORNL for post-processing MFIX output to efficiently summarize the important information generated by the coater simulations. The summarized information includes quantitative spatial and temporal measures (referred to as discriminating characteristics, or DCs) by which different coater designs and operating conditions can be compared and correlated with trends in product quality. The ORNL FBCVD modeling work is being conducted in conjunction with experimental coater studies at ORNL with natural uranium CO (NUCO) and surrogate fuel kernels. Data are also being obtained from ambient-temperature, spouted-bed characterization experiments at the University of Tennessee and theoretical studies of carbon and silicon carbide chemical vapor deposition kinetics at Iowa State University. Prior to the current scale-up activity, considerable effort has gone in to adapting the MFIX code to incorporate the unique features of fuel coating reactors and also in validating the resulting simulation features with experimental observations. Much of this work is documented in previous AGR reports and publications (Pannala et al., 2004, Pannala et al., 2005, Boyalakuntla et al., 2005a, Boyalakuntla et al., 2005b and Finney et al., 2005). As a result of the previous work described above, the ORNL coater model now has the capability for simulating full spatio-temporal details of the gas-particle hydrodynamics and gas-particle heat and mass transfer in the TRISO coater. This capability provides a great deal of information about many of the processes believed to control quality, but the model is not yet sufficiently developed to fully predict coating quality for any given coater design and/or set of operating conditions because the detailed chemical reaction kinetics needed to make the model fully predictive are not yet available. Nevertheless, the model at its current stage of development already provides the most comprehensive and detailed quantitative information available about gas flows, solid flows, temperatures, and species inside the coater during operation. This level of information ought to be highly useful in expediting the scale-up process (e.g., in correlating observations and minimizing the number of pilot-scale tests required). However, previous work had not yet demonstrated that the typical design and/or operating changes known to affect product quality at the lab scale could be clearly discriminated by the existing model. The Modeling Scale-Up Phase I work was initiated to produce such a demonstration, and two detailed examples are discussed in this report.

  8. US LMFBR (Liquid Metal Fast Breeder Reactor): flow induced vibration program (1977-1986): A summary and overview

    SciTech Connect (OSTI)

    Wambsganss, M.W.; Chen, S.S.; Mulcahy, T.M.; Jendrzejczyk, J.A.

    1986-09-01T23:59:59.000Z

    This paper summarizes the activities and accomplishments under the US LMFBR Flow Induced Vibration Program for the period 1977-1986. Since 1977 represents the date of the last IAEA IWGFR Specialists Meeting on LMFBR Flow Induced Vibration, this paper thus provides an update to the results presented at that meeting. This period also represents a period of substantial change for the US LMFBR program. A major reactor project, the FFTF, was completed and a second major project, the CRBR plant, was terminated. This change adversely impacted the US flow induced vibration program. Nevertheless, base technology activities have continued. In this paper, research in the following areas is summarized: Vibration characteristics and scaling, Turbulent buffeting and vortex shedding, Fluidelastic instabilities of tube bundles in crossflow, and Instabilities induced by leakage flows.

  9. Datacenter Sustainability Page 1 Sustainability

    E-Print Network [OSTI]

    Chaudhuri, Surajit

    Datacenter Sustainability Page 1 Datacenter Sustainability #12;Datacenter Sustainability Page 2 sustainability imperative and how advanced technologies, smart business practices, and strategic partnerships are helping us reduce our impact on the environment. Also learn how our investments in efficient, sustainable

  10. Bootstrapping a Sustainable North American PEM Fuel Cell Industry: Could a Federal Acquisition Program Make a Difference?

    SciTech Connect (OSTI)

    Greene, David L [ORNL; Duleep, Dr. K. G. [Energy and Environmental Analysis, Inc., an ICF Company

    2008-10-01T23:59:59.000Z

    The North American Proton Exchange Membrane (PEM) fuel cell industry may be at a critical juncture. A large-scale market for automotive fuel cells appears to be several years away and in any case will require a long-term, coordinated commitment by government and industry to insure the co-evolution of hydrogen infrastructure and fuel cell vehicles (Greene et al., 2008). The market for non-automotive PEM fuel cells, on the other hand, may be much closer to commercial viability (Stone, 2006). Cost targets are less demanding and manufacturers appear to be close, perhaps within a factor of two, of meeting them. Hydrogen supply is a significant obstacle to market acceptance but may not be as great a barrier as it is for hydrogen-powered vehicles due to the smaller quantities of hydrogen required. PEM fuel cells appear to be potentially competitive in two markets: (1) Backup power (BuP) supply, and (2) electrically-powered MHE (Mahadevan et al., 2007a, 2007b). There are several Original Equipment Manufacturers (OEMs) of PEM fuel cell systems for these applications but production levels have been quite low (on the order of 100-200 per year) and cumulative production experience is also limited (on the order of 1,000 units to date). As a consequence, costs remain above target levels and PEM fuel cell OEMs are not yet competitive in these markets. If cost targets can be reached and acceptable solutions to hydrogen supply found, a sustainable North American PEM fuel cell industry could be established. If not, the industry and its North American supply chain could disappear within a year or two. The Hydrogen Fuel Cell and Infrastructure Technologies (HFCIT) program of the U.S. Department of Energy (DOE) requested a rapid assessment of the potential for a government acquisition program to bootstrap the market for non-automotive PEM fuel cells by driving down costs via economies of scale and learning-by-doing. The six week study included in-depth interviews of three manufacturers, visits to two production facilities, review of the literature on potential markets in North America and potential federal government procurements, development of a cost model reflecting economies of scale and learning-by-doing, and estimation of the impact of federal PEM fuel cell procurements on fuel cell system costs and the evolution of private market demand. This report presents the findings of that study. Section 2 outlines the status of the industry and describes potential markets based on interviews of manufacturers and the existing literature. Section 3 describes the modeling methodology including key premises and assumptions, and presents estimates of market evolution under four scenarios: (1) Base Case with no federal government procurement program, (2) Scenario 1, an aggressive program beginning with less than 200 units procured in 2008 ramping up to more than 2,000 units in 2012, (3) Scenario 2 which is identical to Scenario 1 except that the private market is assumed to be twice as sensitive to price, and (4) Scenario 3, a delayed, smaller federal procurement program beginning in 2011 increasing to a maximum of just over 1,000 units per year in 2012. The analysis suggests that the aggressive program of Scenario 1 would likely stimulate a sustainable, competitive North American non-automotive PEM fuel cell industry. Given plausible assumptions about learning rates and scale economies, the procurements assumed in Scenario 1 appear to be sufficient to drive down costs to target levels. These findings are conditional on the evolution of acceptable hydrogen supply strategies, which were not explicitly analyzed in this study. Success is less certain under Scenarios 2 and 3, and there appears to be a strong probability that existing OEMs would not survive until 2011. In the Base Case, no program, a viable North American industry does not emerge before 2020.

  11. Light water reactor safety research program. Seniannual report, October 1981-March 1982

    SciTech Connect (OSTI)

    Not Available

    1982-12-01T23:59:59.000Z

    Information is presented concerning molten fuel-concrete interactions study; core melt-coolant interactions; containment emergency sump performance; hydrogen program; and combustible gas in containment program.

  12. Reactor-safety research programs. Quarterly report, July-September 1982

    SciTech Connect (OSTI)

    Edler, S.K. (ed.)

    1983-03-01T23:59:59.000Z

    Evaluations of nondestructive examination (NDE) techniques and instrumentation are reported; areas of investigation include demonstrating the feasibility of determining the strength of structural graphite, evaluating the feasibility of detecting and analyzing flaw growth in reactor pressure boundary systems, examining NDE reliability and probabilistic fracture mechanics, and assessing the integrity of pressurized water reactor steam generator tubes where service-induced degradation has been indicated. Experimental data and analytical models are being provided to aid in decision-making regarding pipe-to-pipe impacts following postulated breaks in high-energy fluid system piping. Core thermal models are being developed to provide better digital codes to compute the behavior of full-scale reactor systems under postulated accident conditions.

  13. Reactor safety research programs. Volume 1. Quarterly report, January-March 1983

    SciTech Connect (OSTI)

    Edler, S.K. (ed.)

    1983-07-01T23:59:59.000Z

    This document summarizes work performed by Pacific Northwest Laboratory from January 1 through March 31, 1983, for the Division of Accident Evaluation and the Division of Engineering Technology, US Nuclear Regulatory Commission. Evaluation of nondestructive examination (NDE) techniques and instrumentation are reported; areas of investigation include demonstrating the feasibility of determining the strength of structural graphite, evaluating the feasibility of detecting and analyzing flaw growth in reactor pressure boundary systems, examining NDE reliability and probabilistic fracture mechanics, and assessing the integrity of pressurized water reactor steam generator tubes where service-induced degradation has been indicated. Experimental data and analytical models are being provided to aid in decision making regarding pipe-to-pipe impacts following postulated breaks in high-energy fluid system piping. Core thermal models are being developed to provide better digital codes to compute the behavior of full-scale reactor systems under postulated accident conditions.

  14. Gas-Cooled Thermal Reactor Program. Semiannual technical progress report, April 1, 1983-September 30, 1983

    SciTech Connect (OSTI)

    Not Available

    1983-12-01T23:59:59.000Z

    An assessment of the HTGR opportunities from the year 2000 through 2045 was the principal activity on the Market Definition Task (WBS 03). Within the Plant Technology (WBS 13) task, there were activities to develop analytical methods for investigation of Coolant Transport Behavior and to define methods and criteria for High Temperature Structural Engineering design. The activities in support of the HTGR-SC/C Lead Plant (WBS 30 and 31) were the participation in the Lead Plant System Engineering (LPSE) effort and the plant simulation task. The efforts on the Advanced HTGR systems was performed under the Modular Reactor Systems (MRS) (WBS 41) to study the potential for multiple small reactors to provide lower costs, improved safety, and higher availability than the large monolithic core reactors.

  15. R and D program for core instrumentation improvements devoted for French sodium fast reactors

    SciTech Connect (OSTI)

    Jeannot, J. P.; Rodriguez, G.; Jammes, C.; Bernardin, B.; Portier, J. L.; Jadot, F. [Commissariat a l'Energie Atomique, Saint-Paul-lez-Durance, 13108 (France); Maire, S.; Verrier, D. [Advanced Projects and Decommissioning Div. Plant Sector AREVA NP - NEPL-FT, Lyon, 69000 (France); Loisy, F. [EDF - EDF R and D STEP Dept., 6 Quai Watier, Chatou, 78401 (France); Prele, G. [EDF, Generation/Nuclear Engineering, Basic Design Dept., Villeurbanne, 69628 (France)

    2011-07-01T23:59:59.000Z

    Under the framework of French R and D studies for Generation IV reactors and more specifically for sodium-cooled fast reactors (SFR); the CEA, EDF and AREVA have launched a joint coordinated research programme. This paper deals with the R and D sets out to achieve better inspection, maintenance, availability and decommissioning. In particular the instrumentation requirements for core monitoring and detection in the case of accidental events. Requirements mainly involve diversifying the means of protection and improving instrumentation performance in terms of responsiveness and sensitivity. Operation feedback from the Phenix and Superphenix prototype reactors and studies, carried out within the scope of the EFR projects, has been used to define the needs for instrumentation enhancement. (authors)

  16. Light Water Reactor Sustainability Newsletter

    Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

    the operation of commercial nuclear power plants require conservative mar- gins of fracture toughness for the RPV materials, both during normal operation and under accident...

  17. Light Water Reactor Sustainability Newsletter

    Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

    The small volume required for such analysis is beneficial for correlating with the small-scale mechanical testing currently being investigated. Further studies on the...

  18. Liquid Metal Reactor Program: JASPER US/DOE/PNC Shielding Research Program : Technical progress report, April 1-May 31, 1987

    SciTech Connect (OSTI)

    Ingersoll, D.T.; Engle, W.W.; Muckenthaler, F.J.; Slater, C.O.

    1987-12-31T23:59:59.000Z

    This progress report details activities on the JASPER Shielding Program for the time period of April 1, 1987 through May 31, 1987.

  19. Assessment of the high temperature fission chamber technology for the French fast reactor program

    SciTech Connect (OSTI)

    Jammes, C.; Filliatre, P.; Geslot, B.; Domenech, T.; Normand, S. [Commissariat a l'Energie Atomique, CEA (France)

    2011-07-01T23:59:59.000Z

    High temperature fission chambers are key instruments for the control and protection of the sodium-cooled fast reactor. First, the developments of those neutron detectors, which are carried out either in France or abroad are reviewed. Second, the French realizations are assessed with the use of the technology readiness levels in order to identify tracks of improvement. (authors)

  20. Sustainable Development

    E-Print Network [OSTI]

    Brierley, Andrew

    160 Sustainable Development Sustainable Development Degree options BSc or MA (Single Honours Degree) Sustainable Development Contributing Schools Biology; Chemistry; Computer Science; Geography & Geosciences in arts subjects as partner subjects within Sustainable Development, then you should apply for the MA

  1. A REPORT TO THE PRESIDENT ON Sustainability

    E-Print Network [OSTI]

    Johnston, Daniel

    , green building, sustainable building occupant behavior, maintenance and restoration of natural future sustainability projects and the development of a comprehensive training program. BackgroundA REPORT TO THE PRESIDENT ON Sustainability Presented by The University of Texas at Austin Staff

  2. Heavy-Section Steel Irradiation Program on irradiation effects in light-water reactor pressure vessel materials

    SciTech Connect (OSTI)

    Nanstad, R.K.; Corwin, W.R.; Alexander, D.J.; Haggag, F.M.; Iskander, S.K.; McCabe, D.E.; Sokolov, M.A.; Stoller, R.E. [Oak Ridge National Lab., TN (United States). Metals and Ceramics Div.

    1995-07-01T23:59:59.000Z

    The safety of commercial light-water nuclear plants is highly dependent on the structural integrity of the reactor pressure vessel (RPV). In the absence of radiation damage to the RPV, fracture of the vessel is difficult to postulate. Exposure to high energy neutrons can result in embrittlement of radiation-sensitive RPV materials. The Heavy-Section Steel Irradiation (HSSI) Program at Oak Ridge National Laboratory, sponsored by the US Nuclear Regulatory Commission (USNRC), is assessing the effects of neutron irradiation on RPV material behavior, especially fracture toughness. The results of these and other studies are used by the USNRC in the evaluation of RPV integrity and regulation of overall nuclear plant safety. In assessing the effects of irradiation, prototypic RPV materials are characterized in the unirradiated condition and exposed to radiation under varying conditions. Mechanical property tests are conducted to provide data which can be used in the development of guidelines for structural integrity evaluations, while metallurgical examinations and mechanistic modeling are performed to improve understanding of the mechanisms responsible for embrittlement. The results of these investigations, in conjunction with results from commercial reactor surveillance programs, are used to develop a methodology for the prediction of radiation effects on RPV materials. This irradiation-induced degradation of the materials can be mitigated by thermal annealing, i.e., heating the RPV to a temperature above that of normal operation. Thus, thermal annealing and evaluation of reirradiation behavior are major tasks of the HSSI Program. This paper describes the HSSI Program activities by summarizing some past and recent results, as well as current and planned studies. 30 refs., 8 figs., 1 tab.

  3. Evaluation of anticipatory signal to steam generator pressure control program for 700 MWe Indian pressurized heavy water reactor

    SciTech Connect (OSTI)

    Pahari, S.; Hajela, S.; Rammohan, H. P.; Malhotra, P. K.; Ghadge, S. G. [Nuclear Power Corporation of India Limited, Nabhikiya Urja Bhavan, Anushakti Nagar, Mumbai, PIN-400094 (India)

    2012-07-01T23:59:59.000Z

    700 MWe Indian Pressurized Heavy Water Reactor (IPHWR) is horizontal channel type reactor with partial boiling at channel outlet. Due to boiling, it has a large volume of vapor present in the primary loops. It has two primary loops connected with the help of pressurizer surge line. The pressurizer has a large capacity and is partly filled by liquid and partly by vapor. Large vapor volume improves compressibility of the system. During turbine trip or load rejection, pressure builds up in Steam Generator (SG). This leads to pressurization of Primary Heat Transport System (PHTS). To control pressurization of SG and PHTS, around 70% of the steam generated in SG is dumped into the condenser by opening Condenser Steam Dump Valves (CSDVs) and rest of the steam is released to the atmosphere by opening Atmospheric Steam Discharge Valves (ASDVs) immediately after sensing the event. This is accomplished by adding anticipatory signal to the output of SG pressure controller. Anticipatory signal is proportional to the thermal power of reactor and the proportionality constant is set so that SG pressure controller's output jacks up to ASDV opening range when operating at 100% FP. To simulate this behavior for 700 MWe IPHWR, Primary and secondary heat transport system is modeled. SG pressure control and other process control program have also been modeled to capture overall plant dynamics. Analysis has been carried out with 3-D neutron kinetics coupled thermal hydraulic computer code ATMIKA.T to evaluate the effect of the anticipatory signal on PHT pressure and over all plant dynamics during turbine trip in 700 MWe IPHWR. This paper brings out the results of the analysis with and without considering anticipatory signal in SG pressure control program during turbine trip. (authors)

  4. Progress in the United States Liquid Metal Fast Breeder Reactor development program

    SciTech Connect (OSTI)

    Longenecker, J.R.

    1981-01-01T23:59:59.000Z

    Determining the most-logical LMFBR program strategy that can bring the technology to a state of commercial readiness in a timely and cost-effective manner is discussed. Realizing the uncertainties in the need date for the LMFBR, an approach is described which will pursue a program during the next decade that builds on the existing program experience, and that will achieve results that provide the program flexibility to accommodate a range of commercial introduction dates.

  5. Light Water Reactor Sustainability Program Operator Performance Metrics for Control Room Modernization: A Practical Guide for Early Design Evaluation

    SciTech Connect (OSTI)

    Ronald Boring; Roger Lew; Thomas Ulrich; Jeffrey Joe

    2014-03-01T23:59:59.000Z

    As control rooms are modernized with new digital systems at nuclear power plants, it is necessary to evaluate the operator performance using these systems as part of a verification and validation process. There are no standard, predefined metrics available for assessing what is satisfactory operator interaction with new systems, especially during the early design stages of a new system. This report identifies the process and metrics for evaluating human system interfaces as part of control room modernization. The report includes background information on design and evaluation, a thorough discussion of human performance measures, and a practical example of how the process and metrics have been used as part of a turbine control system upgrade during the formative stages of design. The process and metrics are geared toward generalizability to other applications and serve as a template for utilities undertaking their own control room modernization activities.

  6. Light Water Reactor Sustainability Program Technical Basis Guide Describing How to Perform Safety Margin Configuration Risk Management

    SciTech Connect (OSTI)

    Curtis Smith; James Knudsen; Bentley Harwood

    2013-08-01T23:59:59.000Z

    The INL has carried out a demonstration of the RISMC approach for the purpose of configuration risk management. We have shown how improved accuracy and realism can be achieved by simulating changes in risk – as a function of different configurations – in order to determine safety margins as the plant is modified. We described the various technical issues that play a role in these configuration-based calculations with the intent that future applications can take advantage of the analysis benefits while avoiding some of the technical pitfalls that are found for these types of calculations. Specific recommendations have been provided on a variety of topics aimed at improving the safety margin analysis and strengthening the technical basis behind the analysis process.

  7. Shippingport operations with the Light Water Breeder Reactor core. (LWBR Development Program)

    SciTech Connect (OSTI)

    Budd, W.A. (ed.)

    1986-03-01T23:59:59.000Z

    This report describes the operation of the Shippingport Atomic Power Station during the LWBR (Light Water Breeder Reactor) Core lifetime. It also summarizes the plant-oriented operations during the period preceding LWBR startup, which include the defueling of The Pressurized Water Reactor Core 2 (PWR-2) and the installation of the LWBR Core, and the operations associated with the defueling of LWBR. The intent of this report is to examine LWBR experience in retrospect and present pertinent and significant aspects of LWBR operations that relate primarily to the nuclear portion of the Station. The nonnuclear portion of the Station is discussed only as it relates to overall plant operation or to unusual problems which result from the use of conventional equipment in radioactive environments. 30 refs., 69 figs., 27 tabs.

  8. Light water reactor safety research program. Quarterly report Jan-Mar 80

    SciTech Connect (OSTI)

    Berman, M.

    1980-09-01T23:59:59.000Z

    The Molten Fuel Concrete Interactions (MFCI) study is comprised of experimental and analytical investigations of the chemical and physical phenomena associated with interactions between molten core materials and concrete. Such interactions are possible during hypothetical fuel-melt accidents in light water reactors (LWRs) when molten fuel and steel from the reactor core penetrate the pressure vessel and cascade onto the concrete substructure. The purpose of the MFCI study is to develop an understanding of these interactions suitable for risk assessment. Emphasis is placed on identifying and investigating the dominant interaction phenomena occurring between prototypic materials. The table of contents is the following: Molten fuel concrete interactions study; Steam explosion phenomena; Separate effects tests for TRAP code development; and Containment emergency sump performance.

  9. End-of-life destructive examination of light water breeder reactor fuel rods (LWBR Development Program)

    SciTech Connect (OSTI)

    Richardson, K.D.

    1987-10-01T23:59:59.000Z

    Destructive examination of 12 representative Light Water Breeder Reactor fuel rods was performed following successful operation in the Shippingport Atomic Power Station for 29,047 effective full power hours, about five years. Light Water Breeder Reactor fuel rods were unique in that the thorium oxide and uranium-233 oxide fuel was contained within Zircaloy-4 cladding. Destructive examinations included analysis of released fission gas; chemical analysis of the fuel to determine depletion, iodine, and cesium levels; chemical analysis of the cladding to determine hydrogen, iodine, and cesium levels; metallographic examination of the cladding, fuel, and other rod components to determine microstructural features and cladding corrosion features; and tensile testing of the irradiated cladding to determine mechanical strength. The examinations confirmed that Light Water Breeder Reactor fuel rod performance was excellent. No evidence of fuel rod failure was observed, and the fuel operating temperature was low (below 2580/sup 0/F at which an increased percentage of fission gas is released). 21 refs., 80 figs., 20 tabs.

  10. Nuclear proliferation and civilian nuclear power. Report of the Nonproliferation Alternative Systems Assessment Program. Volume IX. Reactor and fuel cycle description

    SciTech Connect (OSTI)

    Not Available

    1980-06-01T23:59:59.000Z

    The Nonproliferation Alterntive Systems Assessment Program (NASAP) has characterized and assessed various reactor/fuel-cycle systems. Volume IX provides, in summary form, the technical descriptions of the reactor/fuel-cycle systems studied. This includes the status of the system technology, as well as a discussion of the safety, environmental, and licensing needs from a technical perspective. This information was then used in developing the research, development, and demonstration (RD and D) program, including its cost and time frame, to advance the existing technology to the level needed for commercial use. Wherever possible, the cost data are given as ranges to reflect the uncertainties in the estimates.

  11. US Liquid Metal Fast Breeder Reactor man-machine interface program

    SciTech Connect (OSTI)

    Vaurio, J.K.; Change, S.A.

    1982-01-01T23:59:59.000Z

    The US LMFBR Man-Machine Interface Program is supportive to and an integral part of the LMFBR Safety Program. This paper describes the goal and objectives of the program, and the necessary research and development efforts with a logical structure for the orderly and timely implementation of the prgoram. Current status and near-term and long-term priority activities are also summarized.

  12. Advanced Light Water Reactor Plants System 80+{trademark} Design Certification Program. Annual progress report, October 1, 1992--September 30, 1993

    SciTech Connect (OSTI)

    Not Available

    1993-12-31T23:59:59.000Z

    The purpose of this report is to provide a status of the progress that was made towards Design Certification of System 80+{trademark} during the US government`s 1993 fiscal year. The System 80+ Advanced Light Water Reactor (ALWR) is a 3931 MW{sub t} (1350 MWe) Pressurized Water Reactor (PWR). The design consists of an essentially complete plant. It is based on evolutionary improvements to the Standardized System 80 nuclear steam supply system in operation at Palo Verde Units 1, 2, and 3, and the Duke Power Company P-81 balance-of-plant (BOP) that was designed and partially constructed at the Cherokee plant site. The System 80/P-81 original design has been substantially enhanced to increase conformance with the EPRI ALWR Utility Requirements Document (URD). Some design enhancements incorporated in the System 80+ design are included in the four units currently under construction in the Republic of Korea. These units form the basis of the Korean standardization program. The full System 80+ standard design has been offered to the Republic of China, in response to their recent bid specification. The ABB-CE Standard Safety Analysis Report (CESSAR-DC) was submitted to the NRC and a Draft Safety Evaluation Report was issued by the NRC in October 1992. CESSAR-DC contains the technical basis for compliance with the EPRI URD for simplified emergency planning. The Nuclear Steam Supply System (NSSS) is the standard ABB-Combustion Engineering two-loop arrangement with two steam generators, two hot legs and four cold legs each with a reactor coolant pump. The System 80+ standard plant includes a sperical steel containment vessel which is enclosed in a concrete shield building, thus providing the safety advantages of a dual containment.

  13. Technology Development Program for an Advanced Potassium Rankine Power Conversion System Compatible with Several Space Reactor Designs

    SciTech Connect (OSTI)

    Yoder, G.L.

    2005-10-03T23:59:59.000Z

    This report documents the work performed during the first phase of the National Aeronautics and Space Administration (NASA), National Research Announcement (NRA) Technology Development Program for an Advanced Potassium Rankine Power Conversion System Compatible with Several Space Reactor Designs. The document includes an optimization of both 100-kW{sub e} and 250-kW{sub e} (at the propulsion unit) Rankine cycle power conversion systems. In order to perform the mass optimization of these systems, several parametric evaluations of different design options were investigated. These options included feed and reheat, vapor superheat levels entering the turbine, three different material types, and multiple heat rejection system designs. The overall masses of these Nb-1%Zr systems are approximately 3100 kg and 6300 kg for the 100- kW{sub e} and 250-kW{sub e} systems, respectively, each with two totally redundant power conversion units, including the mass of the single reactor and shield. Initial conceptual designs for each of the components were developed in order to estimate component masses. In addition, an overall system concept was presented that was designed to fit within the launch envelope of a heavy lift vehicle. A technology development plan is presented in the report that describes the major efforts that are required to reach a technology readiness level of 6. A 10-year development plan was proposed.

  14. City of Jacksonville- Sustainable Public Buildings

    Broader source: Energy.gov [DOE]

    In 2009, the Jacksonville City Office of Sustainability Initiatives announced the creation of the Sustainable Building Program. As part of the program, all new city-owned buildings must meet...

  15. High Performance Sustainable Building

    Broader source: Directives, Delegations, and Requirements [Office of Management (MA)]

    2011-11-09T23:59:59.000Z

    This Guide provides approaches for implementing the High Performance Sustainable Building (HPSB) requirements of DOE Order 413.3B, Program and Project Management for the Acquisition of Capital Assets. Cancels DOE G 413.3-6.

  16. Sustainable Development

    E-Print Network [OSTI]

    Brierley, Andrew

    150 Sustainable Development Sustainable Development MA or BSc (Single Honours Degree) Sustainable Sustainable Development, then you should apply for the MA degree, and students most interested in Science subjects as partner subjects within Sustainable Development should apply for the BSc degree. Subject

  17. Interagency Sustainability Working Group Members

    Broader source: Energy.gov [DOE]

    Chaired by the Federal Energy Management Program, the Interagency Sustainability Working Group is composed of representatives from every major Federal agency.

  18. Light Water Reactor Safety Technology Program. Quarterly report, October-December 1979

    SciTech Connect (OSTI)

    None

    1980-06-01T23:59:59.000Z

    Information on LWR safety is presented concerning the Technology Management Center support programs; risk methods utilization; improved safety systems;man-machine interaction; safety data; and progress reports for each of the research project areas.

  19. Reactor safety research programs. Quarterly report, July 1-September 30, 1979

    SciTech Connect (OSTI)

    Hooper, J.L. (comp.)

    1980-03-01T23:59:59.000Z

    The programs include: ultimate heat sink performance measurement; experimental verification of steady state codes: Task A - irradiation results and Task C - code development; graphite nondestructive testing; acoustic emission-flaw relationship for in-service monitoring of nuclear pressure vessels; fuel subassembly procurement and irradiation test program; report of resident engineer at Cadarache, France; core thermal model development; integration of nondestructive examination reliability and fracture mechanics; and steam generator tube integrity.

  20. DCP is national sustainability leader

    E-Print Network [OSTI]

    Pilyugin, Sergei S.

    UF Voices DCP is national sustainability leader Yesterday, Oct. 26, the College of Design, Construc-Orlando. Located in down- town Orlando, the program will bring sustainable design training to urban challenges approaches to sustainability. Another example is the international competition, Solar Decathlon Europe

  1. Master of science in Sustainability

    E-Print Network [OSTI]

    Master of science in Sustainability Management #12;"As someone who is passionate about sustainability, I want my work to have an impact and I know my future efforts will have an even greater impact on society with the knowledge and experience I gain from the program." --Davida Heller, Sustainability

  2. Light Water Breeder Reactor fuel rod design and performance characteristics (LWBR Development Program)

    SciTech Connect (OSTI)

    Campbell, W.R.; Giovengo, J.F.

    1987-10-01T23:59:59.000Z

    Light Water Breeder Reactor (LWBR) fuel rods were designed to provide a reliable fuel system utilizing thorium/uranium-233 mixed-oxide fuel while simultaneously minimizing structural material to enhance fuel breeding. The fuel system was designed to be capable of operating successfully under both load follow and base load conditions. The breeding objective required thin-walled, low hafnium content Zircaloy cladding, tightly spaced fuel rods with a minimum number of support grid levels, and movable fuel rod bundles to supplant control rods. Specific fuel rod design considerations and their effects on performance capability are described. Successful completion of power operations to over 160 percent of design lifetime including over 200 daily load follow cycles has proven the performance capability of the fuel system. 68 refs., 19 figs., 44 tabs.

  3. Fuel development activities of the US RERTR Program. [Reduced Enrichment Research and Test Reactor

    SciTech Connect (OSTI)

    Snelgrove, J.L.; Domagala, R.F.; Wiencek, T.C.; Copeland, G.L.

    1983-01-01T23:59:59.000Z

    Progress in the development and irradiation testing of high-density fuels for use with low-enriched uranium in research and test reactors is reported. Swelling and blister-threshold temperature data obtained from the examination of miniature fuel plates containing UAl/sub x/, U/sub 3/O/sub 8/, U/sub 3/Si/sub 2/, or U/sub 3/Si dispersed in an aluminum matrix are presented. Combined with the results of metallurgical examinations, these data show that these four fuel types will perform adequately to full burnup of the /sup 235/U contained in the low-enriched fuel. The exothermic reaction of the uranium-silicide fuels with aluminum has been found to occur at about the same temperature as the melting of the aluminum matrix and cladding and to be essentially quenched by the melting endotherm. A new series of miniature fuel plate irradiations is also discussed.

  4. Sustainability Support

    Broader source: Energy.gov [DOE]

    Sustainability Support serves as a corporate technical assistance, coordination, and integration resource to support line organizations in the resolution of sustainability issues and management concerns.

  5. PhD in Sustainable Development PhD in Sustainable Development

    E-Print Network [OSTI]

    Qian, Ning

    PhD in Sustainable Development PhD in Sustainable Development 2013-2014 Handbook John Colin Mutter................................................................................................ 39 #12;3 PhD in Sustainable Development I. About the Program The sustainability of development in the social, natural, engineering or health sciences. The PhD in Sustainable Development combines

  6. Sustainably Priced Energy Enterprise Development (SPEED) Goals

    Broader source: Energy.gov [DOE]

    Vermont's Sustainably Priced Energy Enterprise Development (SPEED) Program was created by legislation in 2005 to promote renewable energy development. The SPEED program itself is not a renewable...

  7. RERTR program activities related to the development and application of new LEU fuels. [Reduced Enrichment Research and Test Reactor; low-enriched uranium

    SciTech Connect (OSTI)

    Travelli, A.

    1983-01-01T23:59:59.000Z

    The statue of the U.S. Reduced Enrichment Research and Test Reactor (RERTR) Program is reviewed. After a brief outline of RERTR Program objectives and goals, program accomplishments are discussed with emphasis on the development, demonstration and application of new LEU fuels. Most program activities have proceeded as planned, and a combination of two silicide fuels (U/sub 3/Si/sub 2/-Al and U/sub 3/Si-Al) holds excellent promise for achieving the long-term program goals. Current plans and schedules project the uranium density of qualified RERTR fuels for plate-type reactors to grow by approximately 1 g U/cm/sup 3/ each year, from the current 1.7 g U/cm/sup 3/ to the 7.0 g U/cm/sup 3/ which will be reached in late 1988. The technical needs of research and test reactors for HEU exports are also forecasted to undergo a gradual but dramatic decline in the coming years.

  8. Light-water-reactor safety materials engineering research programs. Quarterly progress report, January-March 1985. Volume 1

    SciTech Connect (OSTI)

    Not Available

    1986-03-01T23:59:59.000Z

    This progress report summarizes work performed by the Materials Science and Technology Division of Argonne National Laboratory during January, February, and March 1985 on water reactor safety problems. The research and development areas covered are Environmentally Assisted Cracking in Light-Water Reactors and Long-Term Embrittlement of Cast Duplex Stainless Steels in Light-Water-Reactor Systems. 42 refs.

  9. Light-water-reactor safety materials engineering research programs. Volume 3. Quarterly progress report, October-December 1984

    SciTech Connect (OSTI)

    Not Available

    1985-10-01T23:59:59.000Z

    This progress report summarizes work performed by the Materials Science and Technology Division of Argonne National Laboratory during October, November, and December 1984 on water reactor safety problems. The research and development areas covered are Environmentally Assisted Cracking in Light-Water Reactors and Long-Term Embrittlement of Cast Duplex Stainless Steels in Light-Water-Reactor Systems.

  10. Gas cooled fast reactor control rod drive mechanism deceleration unit. Test program

    SciTech Connect (OSTI)

    Wagner, T.H.

    1981-10-01T23:59:59.000Z

    This report presents the results of the airtesting portion of the proof-of-principle testing of a Control Rod Scram Deceleration Device developed for use in the Gas Cooled Fast Reactor (GCFR). The device utilizes a grooved flywheel to decelerate the translating assembly (T/A). Two cam followers on the translating assembly travel in the flywheel grooves and transfer the energy of the T/A to the flywheel. The grooves in the flywheel are straight for most of the flywheel length. Near the bottom of the T/A stroke the grooves are spiraled in a decreasing slope helix so that the cam followers accelerate the flywheel as they transfer the energy of the falling T/A. To expedite proof-of-principle testing, some of the materials used in the fabrication of certain test article components were not prototypic. With these exceptions the concept appears to be acceptable. The initial test of 300 scrams was completed with only one failure and the failure was that of a non-prototypic cam follower outer sleeve material.

  11. compiled by the pacific institute's community strategies for sustainability and justice program GearinG up for acti n

    E-Print Network [OSTI]

    environmental health, justice, and sustainability in low-income neighborhoods and communities of color- and moderate- income residents to exercise greater control over environmental problems that impact in order to make effective, community-based decisions. ditching dirty diesel collaborative (dddc) 510

  12. Preliminary nuclear safety assessment of the NEPST (Topaz II) space reactor program

    SciTech Connect (OSTI)

    Marshall, A.C.

    1993-01-01T23:59:59.000Z

    The United States (US) Strategic Defense Initiative Organization (SDIO) decided to investigate the possibility of launching a Russian Topaz II space nuclear power system. A preliminary nuclear safety assessment was conducted to determine whether or not a space mission could be conducted safely and within budget constraints. As part of this assessment, a safety policy and safety functional requirements were developed to guide both the safety assessment and future Topaz II activities. A review of the Russian flight safety program was conducted and documented. Our preliminary nuclear safety assessment included a number of deterministic analyses, such as; neutronic analysis of normal and accident configurations, an evaluation of temperature coefficients of reactivity, a reentry and disposal analysis, an analysis of postulated launch abort impact accidents, and an analysis of postulated propellant fire and explosion accidents. Based on the assessment to date, it appears that it will be possible to safely launch the Topaz II system in the US with a modification to preclude water flooded criticality. A full scale safety program is now underway.

  13. Individual plant examination program: Perspectives on reactor safety and plant performance. Parts 2--5: Final report; Volume 2

    SciTech Connect (OSTI)

    NONE

    1997-12-01T23:59:59.000Z

    This report provides perspectives gained by reviewing 75 Individual Plant Examination (IPE) submittals pertaining to 108 nuclear power plant units. IPEs are probabilistic analyses that estimate the core damage frequency (CDF) and containment performance for accidents initiated by internal events. The US Nuclear Regulatory Commission (NRC) reviewed the IPE submittals with the objective of gaining perspectives in three major areas: (1) improvements made to individual plants as a result of their IPEs and the collective results of the IPE program, (2) plant-specific design and operational features and modeling assumptions that significantly affect the estimates of CDF and containment performance, and (3) strengths and weaknesses of the models and methods used in the IPEs. These perspectives are gained by assessing the core damage and containment performance results, including overall CDF, accident sequences, dominant contributions to component failure and human error, and containment failure modes. Methods, data, boundary conditions, and assumptions used in the IPEs are considered in understanding the differences and similarities observed among the various types of plants. This report is divided into three volumes containing six parts. Part 1 is a summary report of the key perspectives gained in each of the areas identified above, with a discussion of the NRC`s overall conclusions and observations. Part 2 discusses key perspectives regarding the impact of the IPE Program on reactor safety. Part 3 discusses perspectives gained from the IPE results regarding CDF, containment performance, and human actions. Part 4 discusses perspectives regarding the IPE models and methods. Part 5 discusses additional IPE perspectives. Part 6 contains Appendices A, B and C which provide the references of the information from the IPEs, updated PRA results, and public comments on draft NUREG-1560 respectively.

  14. Undergraduate reactor control experiment

    SciTech Connect (OSTI)

    Edwards, R.M.; Power, M.A.; Bryan, M. (Pennsylvania State Univ., University Park (United States))

    1992-01-01T23:59:59.000Z

    A sequence of reactor and related experiments has been a central element of a senior-level laboratory course at Pennsylvania State University (Penn State) for more than 20 yr. A new experiment has been developed where the students program and operate a computer controller that manipulates the speed of a secondary control rod to regulate TRIGA reactor power. Elementary feedback control theory is introduced to explain the experiment, which emphasizes the nonlinear aspect of reactor control where power level changes are equivalent to a change in control loop gain. Digital control of nuclear reactors has become more visible at Penn State with the replacement of the original analog-based TRIGA reactor control console with a modern computer-based digital control console. Several TRIGA reactor dynamics experiments, which comprise half of the three-credit laboratory course, lead to the control experiment finale: (a) digital simulation, (b) control rod calibration, (c) reactor pulsing, (d) reactivity oscillator, and (e) reactor noise.

  15. Departmental Sustainability

    Broader source: Directives, Delegations, and Requirements [Office of Management (MA)]

    2011-05-02T23:59:59.000Z

    The order defines requirements and responsibilities for managing sustainability DOE to ensure that the Department carries out its missions in a sustainable manner that addresses national energy security and global environmental challenges, and advances sustainable, efficient and reliable energy for the future; institute wholesale cultural change to factor sustainability and greenhouse gas (GHG) reductions into all DOE corporate management decisions; and ensure that DOE achieves the sustainability goals established in its Strategic Sustainability Performance Plan. Cancels DOE O 450.1A and DOE O 430.2B

  16. Sustainable Forward Operating Base Nuclear Power Evaluation (Relationship Mapping System) Users’ Manual

    SciTech Connect (OSTI)

    Not Listed

    2012-01-01T23:59:59.000Z

    The Sustainable Forward Operating Base (FOB) Nuclear Power Evaluation was developed by the Idaho National Laboratory Systems Engineering Department to support the Defense Advanced Research Projects Agency (DARPA) in assessing and demonstrating the viability of deploying small-scale reactors in support of military operations in theatre. This document provides a brief explanation of how to access and use the Sustainable FOB Nuclear Power Evaluation utility to view assessment results as input into developing and integrating the program elements needed to create a successful demonstration.

  17. Materials Science Division light-water-reactor safety research program. Quarterly progress report, January-March 1982

    SciTech Connect (OSTI)

    Shack, W.J.; Rest, J.; Kassner, T.F.

    1982-10-01T23:59:59.000Z

    Information is presented concerning environmentally assisted cracking in light water reactors; transient fuel response and fission product release; and clad properties for code verification.

  18. Light-Water-Reactor Safety Research Program. Quarterly progress report, April-June 1980

    SciTech Connect (OSTI)

    Massey, W.E.; Till, C.E.

    1980-10-01T23:59:59.000Z

    Parametric correlations of two and three variables have been developed to describe GRASS-SST-predicted steady-state fission-gas release from UO/sub 2/-based fuels. The parametric model, PARAGRASS, has the capability of reproducing GRASS-SST results with good accuracy. In future work, other parameters will be included in the model, and the model will be extended to transient analyses. Also, the methods used to develop correlations for fission-gas release will be used to develop correlations for fuel-swelling strain. An assumption used in the GRASS-SST calculation of grain-edge swelling has been found deficient and is being replaced with a more realistic model. Specimens from the ORNL program ''Fission Product Behavior in LWRs'' were sent to ANL-East for a determination of the mechanism of fission-product release during the high-temperature (>1300/sup 0/C) tests. The preliminary examination of the specimens has been completed. 10 refs., 15 figs., 21 tabs.

  19. Final progress report on Grant No. DE-FG02-81ER10229, U.S. Department of Energy Reactor Sharing Program at the University of Wisconsin, July 15, 2000 - May 31, 2001

    SciTech Connect (OSTI)

    Agasie, Robert J.

    2001-12-27T23:59:59.000Z

    The Reactor Sharing Program makes the facilities of the University of Wisconsin Nuclear Reactor Laboratory available to other educational institutions. Uses include direct instruction, student theses projects, and staff research projects. A list of using institutions and a brief description of use is given.

  20. Blueprint for Sustainability - Sustainable Solutions for Every...

    Office of Energy Efficiency and Renewable Energy (EERE) Indexed Site

    Blueprint for Sustainability - Sustainable Solutions for Every Consumer Blueprint for Sustainability - Sustainable Solutions for Every Consumer Highlights of Ford's near, mid, and...

  1. Sustainability at BPA 2013

    SciTech Connect (OSTI)

    none,

    2013-12-01T23:59:59.000Z

    THIS IS THE THIRD YEAR BPA has reported on sustainability program accomplishments. The report provides an opportunity to review progress made on sustainability initiatives, evaluate how far we have come and how much we can improve. The program has demonstrated maturation as the concepts of sustainability and resource conservation are communicated and understood. The sustainability program started as an employee-driven “grass roots” effort in 2010. Sustainability is becoming a consideration in how work is performed. The establishment of several policies supporting sustainability efforts proves the positive progress being made. In 2009, BPA became a founder and member of The Climate Registry, a nonprofit collaboration that sets standards to calculate, verify and report greenhouse gas emissions. This year, BPA completed and published our Greenhouse Gas inventory for the years of 2009, 2010 and 2011. The 2012 inventory is currently in the process of third-party verification and scheduled for public release in January 2014. These inventories provide a concrete measure of the progress we are making.

  2. Living Sustainably

    E-Print Network [OSTI]

    Milbrath, Lester W.

    1998-01-01T23:59:59.000Z

    sustainable society does something more than keep people alive; livingsustainable modes of behavior that also lead to quality in living.

  3. Materials Science and Technology Division light-water-reactor safety research program: quarterly progress report, January-March 1983

    SciTech Connect (OSTI)

    Not Available

    1984-04-01T23:59:59.000Z

    This progress report summarizes the Argonne National Laboratory work performed during January, February and March 1983 on water reactor safety problems. The research and development areas covered are Environmentally Assisted Cracking in Light Water Reactors, Transient Fuel Response and Fission Product Release, Clad Properties for Code Verification, and Long-Term Embrittlement of Cast Duplex Stainless Steels in LWR Systems.

  4. Materials Science Division light-water-reactor safety-research program. Quarterly progress report, April-June 1982. Volume 2

    SciTech Connect (OSTI)

    Shack, W.J.; Rest, J.; Kassner, T.F.; Chung, H.M.; Claytor, T.N.; Kupperman, D.S.; Maiya, P.S.; Nichols, F.A.; Park, J.Y.; Ruther, W.E.; Yaggee, F.L.

    1983-05-01T23:59:59.000Z

    This progress report summarizes the Argonne National Laboratory work performed during April, May, and June 1982 on water-reactor-safety problems. The research and development areas covered are Environmentally Assisted Cracking in Light Water Reactors, Transient Fuel Response and Fission Product Release, and Clad Properties for Code Verification.

  5. Materials Science Division light-water-reactor safety research program. Quarterly progress report, July-September 1982

    SciTech Connect (OSTI)

    Shack, W.J.; Rest, J.; Kassner, T.F.; Neimark, L.A.; Chung, H.M.; Claytor, T.N.; Kupperman, D.S.; Maiya, P.S.; Nichols, F.A.; Park, J.Y.

    1983-08-01T23:59:59.000Z

    This progress report summarizes the Argonne National Laboratory work performed during July, August, and September 1982 on water reactor safety problems. The research and development areas covered are Environmentally Assisted Cracking in Light Water Reactors, Transient Fuel Response and Fission Product Release, Clad Properties for Code Verification, Posttest Fuel Examination of the ORNL Fission Product Release Tests, and Examination of TMI-2 Fuel Specimens.

  6. SUSTAINABLE DEVELOPMENT

    E-Print Network [OSTI]

    van der Torre, Leon

    Report on SUSTAINABLE DEVELOPMENT 2 0 1 1 ­ 2 0 1 2 ISCN-GULF Charter Report #12;3 1. FACILITIES with projects of our University's Cell for Sustainable Development; it also presents evidence for steady alike. THIS REPORT This is the second report on sustainable development at the University of Luxembourg

  7. MMMaaattteeerrriiiaaalllsss SSSeeemmmiiinnnaaarrr Support of Sustainable Energy Research by the

    E-Print Network [OSTI]

    MMMaaattteeerrriiiaaalllsss SSSeeemmmiiinnnaaarrr Support of Sustainable Energy Research by the National Science Foundation Gregory Rorrer Energy for Sustainability Program National Science Foundation Abstract Achieving sustainable production of energy is one of the grand challenges of the 21st century

  8. Guiding Tours of the LA River and Promoting Sustainability

    E-Print Network [OSTI]

    Price, Jenny

    2011-01-01T23:59:59.000Z

    River and Promoting Sustainability T his spring, I’m pleaseds new M.A. in Urban Sustainability program, and excitedlyCSW research scholars Sustainability,” on the central role

  9. Montana State University 1 Sustainable Food &

    E-Print Network [OSTI]

    Maxwell, Bruce D.

    , bioenergy production, marketing, distribution, and local food systems. Sustainable Food Systems OptionMontana State University 1 Sustainable Food & Bioenergy Systems This program is a unique, processing, distribution, and utilization of food and bioenergy. The degree focuses on ecologically sound

  10. Enabling Sustainable Behavior | Interventions in Public Space 

    E-Print Network [OSTI]

    Douville, Carmen

    2012-08-15T23:59:59.000Z

    the urban landscape, can ultimately influence sustainable behavior. This dissertation argues that interventions of bicycle sharing programs and kinetic interactive public lighting are two examples where small objects facilitate pro-sustainable behavior...

  11. "Sustainable energy is critical to Canada's economic future." carleton.ca/sustainable-energy

    E-Print Network [OSTI]

    Dawson, Jeff W.

    "Sustainable energy is critical to Canada's economic future." carleton.ca/sustainable-energy GRADUATE PROGRAMS IN SUSTAINABLE ENERGY SHAPE YOUR FUTURE BASED ON YOUR RESEARCH INTERESTS Sustaining energy production and use is becoming increasingly challenging and requires innovative research into new

  12. SUSTAINABLE A university for sustainable development

    E-Print Network [OSTI]

    Johannesson, Henrik

    THE SUSTAINABLE UNIVERSITY #12;A university for sustainable development The University contribution to a sustainable future. By systematically integrating sustainable development into research. The University of Gothenburg's Vision 2020 confirms that sustainable development is important; we always consider

  13. Metropolitan Accessibility and Transportation Sustainability:Sustainability

    E-Print Network [OSTI]

    Papalambros, Panos

    Metropolitan Accessibility and Transportation Sustainability:Sustainability: Comparative Reduce (fulfillment of)Promote Sustainability: Meet needs of (fulfillment of) needs present Institute SMART Sustainable Mobility and Accessibility Research andSMART Sustainable Mobility

  14. Sustainable Food Sustainable Water Land Use & Wildlife Culture & Commun ble Transport Sustainable Materials Local & Sustainable Food Sustainable Wat

    E-Print Network [OSTI]

    Netoff, Theoden

    Sustainable Food Sustainable Water Land Use & Wildlife Culture & Commun ble Transport Sustainable Materials Local & Sustainable Food Sustainable Wat appiness Zero Carbon Zero Waste Sustainable Transport Sustainable Materia munity Equity & Local Economy Health & Happiness Zero Carbon Zero Was Water Land Use

  15. WWU Sustainability Academy 4PM, Wednesday, December 3, CF 125

    E-Print Network [OSTI]

    Zaferatos, Nicholas C.

    WWU Sustainability Academy 4PM, Wednesday, December 3, CF 125 Agenda 1. WWU Sustainability Academy Sustainability Courses at WWU ­ Gene Myers 4. Existing Sustainability Prototype Programs at WWU ­ Arunas Oslapas faculty member in the Sustainability Academy ¡ 25 Yes ¡ 6 Not sure Anonymous surveyors: ¡ 7 Not sure ¡ 1

  16. Materials Science and Technology Division, light-water-reactor safety research program. Quarterly progress report, October-December 1982

    SciTech Connect (OSTI)

    Shack, W.J.; Rest, J.; Kassner, T.F.; Ayrault, G.; Chopra, O.K.; Chung, H.M.; Kupperman, D.S.; Maiya, P.S.; Nichols, F.A.; Park, J.Y.

    1983-11-01T23:59:59.000Z

    The research and development areas covered are Environmentally Assisted Cracking in Light Water Reactors, Transient Fuel Response and Fission Product Release, Clad Properties for Code Verification, and Long-Term Embrittlement of Cast Duplex Stainless Steels in LWR Systems.

  17. High-temperature gas-cooled reactor technology development program. Annual progress report for period ending December 31, 1980

    SciTech Connect (OSTI)

    Not Available

    1981-08-01T23:59:59.000Z

    Research activities are described concerning HTGR chemistry; fueled graphite development; prestressed concrete pressure vessel development; structural materials; HTGR graphite studies; HTR core evaluation; reactor physics; shielding; application and project assessments; and HTR Core Flow Test Loop studies.

  18. Campus Sustainability at Virginia Tech

    E-Print Network [OSTI]

    Virginia Tech

    together to ensure a more sustainable future for us all. Sincerely, Fred Selby, Energy and Sustainability Internship Program by forming four interdisciplinary teams, comprised of 28 students. These teams utilized. A total of 15 Blacksburg campus Leadership in Energy and Environmental Design (LEED) registered projects

  19. Sustainable Fracking

    Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

    Sustainable Fracking As industry taps unconventional energy resources, DOE can help identify and mitigate risks of new extraction approaches. For example, recovery of the vast...

  20. Technological Transfer from Research Nuclear Reactors to New Generation Nuclear Power Reactors

    SciTech Connect (OSTI)

    Radulescu, Laura ['Horia Hulubei' National Institute of Nuclear Physics and Engineering, PO BOX MG-6, Bucharest 077125 (Romania); Pavelescu, Margarit [Academy of Romanian Scientists, Bucharest (Romania)

    2010-01-21T23:59:59.000Z

    The goal of this paper is the analysis of the technological transfer role in the nuclear field, with particular emphasis on nuclear reactors domain. The presentation is sustained by historical arguments. In this frame, it is very important to start with the achievements of the first nuclear systems, for instant those with natural uranium as fuel and heavy water as moderator, following in time through the history until the New Generation Nuclear Power Reactors.Starting with 1940, the accelerated development of the industry has implied the increase of the global demand for energy. In this respect, the nuclear energy could play an important role, being essentially an unlimited source of energy. However, the nuclear option faces the challenges of increasingly demanding safety requirements, economic competitiveness and public acceptance. Worldwide, a significant amount of experience has been accumulated during development, licensing, construction, and operation of nuclear power reactors. The experience gained is a strong basis for further improvements. Actually, the nuclear programs of many countries are addressing the development of advanced reactors, which are intended to have better economics, higher reliability, improved safety, and proliferation-resistant characteristics in order to overcome the current concerns about nuclear power. Advanced reactors, now under development, may help to meet the demand for energy power of both developed and developing countries as well as for district heating, desalination and for process heat.The paper gives historical examples that illustrate the steps pursued from first research nuclear reactors to present advanced power reactors. Emphasis was laid upon the fact that the progress is due to the great discoveries of the nuclear scientists using the technological transfer.

  1. Venice Sustainability Advisory Panel

    E-Print Network [OSTI]

    2009-01-01T23:59:59.000Z

    Venice Sustainability Advisory PanelFINAL REPORT Venice Sustainability Advisory Panel FinalInvestigator The Venice Sustainability Advisory Panel (

  2. Gas-cooled reactor programs. Fuel-management positioning and accounting module: FUELMANG Version V1. 11, September 1981

    SciTech Connect (OSTI)

    Medlin, T.W.; Hill, K.L.; Johnson, G.L.; Jones, J.E.; Vondy, D.R.

    1982-01-01T23:59:59.000Z

    This report documents the code module FUELMANG for fuel management of a reactor. This code may be used to position fuel during the calculation of a reactor history, maintain a mass balance history of the fuel movement, and calculate the unit fuel cycle component of the electrical generation cost. In addition to handling fixed feed fuel without recycle, provision has been made for fuel recycle with various options applied to the recycled fuel. A continuous fueling option is also available with the code. A major edit produced by the code is a detailed summary of the mass balance history of the reactor and a fuel cost analysis of that mass balance history. This code is incorporated in the system containing the VENTURE diffusion theory neutronics code for routine use. Fuel movement according to prescribed instructions is performed without the access of additional user input data during the calculation of a reactor operating history. Local application has been primarily for analysis of the performance of gas-cooled thermal reactor core concepts.

  3. Extension of load follow capability of a PWR reactor by optimal control

    SciTech Connect (OSTI)

    Winokur, M.; Tepper, L.

    1984-04-01T23:59:59.000Z

    The problem of extending that part of the fuel life cycle during which a reactor is capable of sustaining load-follow operation is formulated as an optimal control problem. A two-node model representation of pressurized water reactor dynamics is used, leading to a set of non-linear ordinary differential equations. Differential Dynamic Programming is used to solve directly the resulting nonlinear optimization problem and obtain the trajectories of soluble boron concentration and control rod insertion. Results of computations performed for a reference reactor are presented, showing how the optimal control policy stretches the capability of the reactor to follow an average daily load curve towards the end of the fuel life cycle.

  4. Energy Efficiency Market Sustainable Business Planning

    Broader source: Energy.gov [DOE]

    Energy Efficiency Market Sustainable Business Planning, a presentation by Danielle Sass Byrnett of the U.S. Department of Energy's Better Buildings Neighborhood Program.

  5. Reactor Materials Program - Baseline Material Property Handbook - Mechanical Properties of 1950's Vintage Stainless Steel Weldment Components, Task Number 89-23-A-1

    SciTech Connect (OSTI)

    Stoner, K.J.

    1999-11-05T23:59:59.000Z

    The Process Water System (primary coolant) piping of the nuclear production reactors constructed in the 1950''s at Savannah River Site is comprised primarily of Type 304 stainless steel with Type 308 stainless steel weld filler. A program to measure the mechanical properties of archival PWS piping and weld materials (having approximately six years of service at temperatures between 25 and 100 degrees C) has been completed. The results from the mechanical testing has been synthesized to provide a mechanical properties database for structural analyses of the SRS piping.

  6. sustainable environment

    E-Print Network [OSTI]

    sustainable resource management environment fisheries aquaculture Cefas capability statement #12 that they can manage their environments and resources in a responsible, effective and sustainable manner. Our costs ¡ Understand, assess and develop opportunities in the short, medium and long-term ¡ Build

  7. TRAC-PF1/MOD1: an advanced best-estimate computer program for pressurized water reactor thermal-hydraulic analysis

    SciTech Connect (OSTI)

    Liles, D.R.; Mahaffy, J.H.

    1986-07-01T23:59:59.000Z

    The Los Alamos National Laboratory is developing the Transient Reactor Analysis Code (TRAC) to provide advanced best-estimate predictions of postulated accidents in light-water reactors. The TRAC-PF1/MOD1 program provides this capability for pressurized water reactors and for many thermal-hydraulic test facilities. The code features either a one- or a three-dimensional treatment of the pressure vessel and its associated internals, a two-fluid nonequilibrium hydrodynamics model with a noncondensable gas field and solute tracking, flow-regime-dependent constitutive equation treatment, optional reflood tracking capability for bottom-flood and falling-film quench fronts, and consistent treatment of entire accident sequences including the generation of consistent initial conditions. The stability-enhancing two-step (SETS) numerical algorithm is used in the one-dimensional hydrodynamics and permits this portion of the fluid dynamics to violate the material Courant condition. This technique permits large time steps and, hence, reduced running time for slow transients.

  8. DOE Sustainability Awards Best Practices Virtual Workshop

    Broader source: Energy.gov [DOE]

    The Sustainability Performance Office (SPO) will host a virtual best practices workshop on April 23, 2014 (2:00-3:30 PM EDT) to recognize the winners of the 2013 DOE Sustainability Awards. Award winners will present on their accomplishments and answer brief questions on their programs and projects. Please join us in celebrating the 2013 DOE Sustainability Awards winners.

  9. Y-12 Site Sustainability Plan

    SciTech Connect (OSTI)

    Spencer, Charles G

    2012-12-01T23:59:59.000Z

    The accomplishments to date and the long-range planning of the Y-12 Energy Management and Sustainability and Stewardship programs support the U.S. Department of Energy (DOE) and the National Nuclear Security Administration (NNSA) vision for a commitment to energy effi ciency and sustainability and to achievement of the Guiding Principles. Specifi cally, the Y-12 vision is to support the Environment, Safety and Health Policy and the DOE Strategic Sustainability Performance Plan, while promoting overall sustainability and reduction of greenhouse gas emissions. The mission of the Y-12 Energy Management program is to incorporate energy-effi cient technologies site-wide and to position Y-12 to meet NNSA energy requirement needs through 2025 and beyond. The plan addresses greenhouse gases, buildings, fleet management, water use, pollution prevention, waste reduction, sustainable acquisition, electronic stewardship and data centers, site innovation and government-wide support.

  10. Light-water-reactor safety fuel systems research programs. Quarterly progress report, January-March 1985. Volume 1

    SciTech Connect (OSTI)

    Not Available

    1986-01-01T23:59:59.000Z

    This progress report summarizes work performed by the Materials Science and Technology Division of Argonne National Laboratory during January, February, and March 1985 on water reactor safety problems related to fuel and cladding. The research and development areas covered are Transient Fuel Response and Fission Product Release and Clad Properties for Code Verification. 15 refs.

  11. Light-water-reactor safety fuel systems research programs. Quarterly progress report, January-March 1984. [Fuel and cladding problems

    SciTech Connect (OSTI)

    Not Available

    1984-09-01T23:59:59.000Z

    This progress report summarizes work performed by the Materials Science and Technology Division of Argonne National Laboratory during January, February, and March 1984 on water reactor safety problems related to fuel and cladding. The research and development areas covered are Transient Fuel Response and Fission Product Release and Clad Properties for Code Verification.

  12. Light-water-reactor safety fuel systems research programs. Quarterly progress report, July-September 1984. Volume 3

    SciTech Connect (OSTI)

    Not Available

    1985-04-01T23:59:59.000Z

    This progress report summarizes work performed by the Materials Science and Technology Division of Argonne National Laboratory during July, August, and September 1984 on water reactor safety problems related to fuel and cladding. The research and development areas covered are Transient Fuel Response and Fission Product Release and Clad Properties for Code Verification. 17 refs., 23 figs., 5 tabs.

  13. Light-water-reactor safety fuel systems research programs. Quarterly progress report, April-June 1984. Volume 2

    SciTech Connect (OSTI)

    Not Available

    1985-02-01T23:59:59.000Z

    This progress report report summarizes work performed by the Materials Science and Technology Division of Argonne National Laboratory during April, May, and June 1984 on water reactor safety problems related to fuel and cladding. The research and development areas covered are Transient Fuel Response and Fission Product Release and Clad Properties for Code Verification.

  14. Light-water-reactor safety fuel systems research programs. Quarterly progress report, October-December 1984. Volume 4

    SciTech Connect (OSTI)

    Not Available

    1985-08-01T23:59:59.000Z

    This progress report summarizes work performed by the Materials Science and Technology Division of Argonne National Laboratory during October, November, and December 1984 on water reactor safety problems related to fuel and cladding. The research and development areas covered are Transient Fuel Response and Fission Product Release and Clad Properties for Code Verification. 30 refs., 23 figs., 2 tabs.

  15. United States Domestic Research Reactor Infrastrucutre TRIGA Reactor Fuel Support

    SciTech Connect (OSTI)

    Douglas Morrell

    2011-03-01T23:59:59.000Z

    The United State Domestic Research Reactor Infrastructure Program at the Idaho National Laboratory manages and provides project management, technical, quality engineering, quality inspection and nuclear material support for the United States Department of Energy sponsored University Reactor Fuels Program. This program provides fresh, unirradiated nuclear fuel to Domestic University Research Reactor Facilities and is responsible for the return of the DOE-owned, irradiated nuclear fuel over the life of the program. This presentation will introduce the program management team, the universities supported by the program, the status of the program and focus on the return process of irradiated nuclear fuel for long term storage at DOE managed receipt facilities. It will include lessons learned from research reactor facilities that have successfully shipped spent fuel elements to DOE receipt facilities.

  16. Reactor Physics

    Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

    Reactor Physics Reactor and nuclear physics is a key area of research at INL. Much of the research done in reactor physics can be separated into one of three categories:...

  17. ENVIRONMENTAL SUSTAINABILITY

    E-Print Network [OSTI]

    , meanwhile, could focus lim- Initiative and Application Model Impact Environmental Information Networ27 ICT AND ENVIRONMENTAL SUSTAINABILITY T he environment is a large complex sys- tem. Managing. Environmental Monitoring and Associated Resource Management and Risk Mitigation ICTimprovestheabilitytoobtain

  18. Science Serving Sustainability

    Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

    Buildings Greening Transportation Green Purchasing & Green Technology Pollution Prevention Science Serving Sustainability ENVIRONMENTAL SUSTAINABILITY GOALS at...

  19. Subchannel Thermal-Hydraulic Experimental Program (STEP). Volume 1. Mixing in a pressurized water reactor (PWR) rod bundle. Final report

    SciTech Connect (OSTI)

    Barber, A.R.; Zielke, L.A.

    1980-08-01T23:59:59.000Z

    This volume describes an experiment that was performed to determine the mixing characteristics of a pressurized water reactor (PWR) rod bundle. The objective of this project was to improve the subchannel computer code models of the reactor core. The experimental technique was isokinetic subchannel withdrawal of the entire flow from two sample subchannels. Once withdrawn, the sample fluid was condensed and its enthalpy was measured by regenerative heat exchange calorimetry. The test bundle was a 4 x 6 electrically heated array with a 50% power upset. The COBRA IIIC code was used to model the experiment and to determine the value of the thermal mixing coefficient, ..beta.., that was necessary to predict the measured results. Both single- and two-phase data were obtained over a range of PWR operating conditions. The results indicate that both single- and two-phase mixing is small. The COBRA model predicts the enthalpy data using a turbulent mixing coefficient, ..beta.. approx. = 0.002.

  20. Sustainabiliity Sustainability Plan

    E-Print Network [OSTI]

    Heller, Barbara

    Sustainabiliity IIT Campus Sustainability Plan 2010­2020 Published Fall Semester 2010 www.iit.edu/campus_sustainability #12;IIT Campus Sustainability Plan 2010-2020 Fall Semester 2010 1 Section I: Background Sustainability ...................................................................................................................................................................8 IIT Academic Entities on Sustainability

  1. Recent Progress in the NSTX/NSTX-U Lithium Program and Prospects for Reactor-Relevant Liquid-Lithium Based Divertor Development

    SciTech Connect (OSTI)

    M. Ono, et al.

    2012-10-27T23:59:59.000Z

    Developing a reactor compatible divertor has been identified as a particularly challenging technology problem for magnetic confinement fusion. While tungsten has been identified as the most attractive solid divertor material, the NSTX/NSTX-U lithium (Li) program is investigating the viability of liquid lithium (LL) as a potential reactor compatible divertor plasma facing component (PFC) . In the near term, operation in NSTX-U is projected to provide reactor-like divertor heat loads < 40 MW/m^2 for 5 s. During the most recent NSTX campaign, ~ 0.85 kg of Li was evaporated onto the NSTX PFCs where a ~50% reduction in heat load on the Liquid Lithium Divertor (LLD) was observed, attributable to enhanced divertor bolometric radiation. This reduced divertor heat flux through radiation observed in the NSTX LLD experiment is consistent with the results from other lithium experiments and calculations. These results motivate an LL-based closed radiative divertor concept proposed here for NSTX-U and fusion reactors. With an LL coating, the Li is evaporated from the divertor strike point surface due to the intense heat. The evaporated Li is readily ionized by the plasma due to its low ionization energies, and the ionized Li ions can radiate strongly, resulting in a significant reduction in the divertor heat flux. Due to the rapid plasma transport in divertor plasma, the radiation values can be significantly enhanced up to ~ 11 MJ/cc of LL. This radiative process has the desired function of spreading the focused divertor heat load to the entire divertor chamber facilitating the divertor heat removal. The LL divertor surface can also provide a "sacrificial" surface to protect the substrate solid material from transient high heat flux such as the ones caused by the ELMs. The closed radiative LLD concept has the advantages of providing some degree of partition in terms of plasma disruption forces on the LL, Li particle divertor retention, and strong divertor pumping action from the Li-coated divertor chamber wall. By operating at a lower temperature than the first wall, the LLD can serve to purify the entire reactor chamber, as impurities generally migrate toward lower temperature Li-condensed surfaces. To maintain the LL purity, a closed LL loop system with a modest capacity (e.g., ~ 1 Liter/sec for ~ 1% level "impurities") is envisioned for a steady-state 1 GW-electric class fusion power plant.

  2. Sustainability Framework 1 Queen's University

    E-Print Network [OSTI]

    Abolmaesumi, Purang

    Sustainability Framework 1 Queen's University Sustainability Strategic Framework #12;Sustainability Framework 2 Contents Introduction .................................................................................................................................................. 2 Queen's Sustainability Mission

  3. Degree Information 37 Transcripted Graduate Certificate Programs

    E-Print Network [OSTI]

    program Energy Sustainability Engineering Certificate Program Graduate Certificate in Advanced's and Gender Studies Certificate Program in Tree Improvement Ocean Observing Systems Certificate Program the student's career goals. Energy Sustainability Engineering Certificate. The graduate level Energy

  4. Energy Modeling of a High Performance Building in the U.A.E. for Sustainability Certification

    E-Print Network [OSTI]

    Jones, M.; Ledinger, S.

    2010-01-01T23:59:59.000Z

    programs. The Leadership in Energy and Environmental Design (LEED) sustainable building program provides a set of criteria for rating sustainable buildings (U.S. Green Building Council 2009). The Estidama rating program, currently in its pilot phase...

  5. Research in nondestructive evaluation techniques for nuclear reactor concrete structures

    SciTech Connect (OSTI)

    Clayton, Dwight; Smith, Cyrus [Oak Ridge National Laboratory, P.O. Box 2008, Oak Ridge, TN 37831 (United States)

    2014-02-18T23:59:59.000Z

    The purpose of the Materials Aging and Degradation (MAaD) Pathway of the Department of Energy's Light Water Reactor Sustainability (LWRS) Program is to develop the scientific basis for understanding and predicting longterm environmental degradation behavior of material in nuclear power plants and to provide data and methods to assess the performance of systems, structures, and components (SSCs) essential to safe and sustained nuclear power plant operations. The understanding of aging-related phenomena and their impacts on SSCs is expected to be a significant issue for any nuclear power plant planning for long-term operations (i.e. service beyond the initial license renewal period). Management of those phenomena and their impacts during long-term operations can be better enable by improved methods and techniques for detection, monitoring, and prediction of SSC degradation. The MAaD Pathway R and D Roadmap for Concrete, 'Light Water Reactor Sustainability Nondestructive Evaluation for Concrete Research and Development Roadmap', focused initial research efforts on understanding the recent concrete issues at nuclear power plants and identifying the availability of concrete samples for NDE techniques evaluation and testing. [1] An overview of the research performed by ORNL in these two areas is presented here.

  6. 2012 Accomplishments Report | Light Water Reactor Sustainability

    Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

    * Completed development plan for silicon carbide (SiC) ceramic matrix composite (CMC) nuclear fuel cladding; this plan will guide future R&D on advanced cladding * Completed...

  7. F Reactor Inspection

    SciTech Connect (OSTI)

    Grindstaff, Keith; Hathaway, Boyd; Wilson, Mike

    2014-10-29T23:59:59.000Z

    Workers from Mission Support Alliance, LLC., removed the welds around the steel door of the F Reactor before stepping inside the reactor to complete its periodic inspection. This is the first time the Department of Energy (DOE) has had the reactor open since 2008. The F Reactor is one of nine reactors along the Columbia River at the Department's Hanford Site in southeastern Washington State, where environmental cleanup has been ongoing since 1989. As part of the Tri-Party Agreement, the Department completes surveillance and maintenance activities of cocooned reactors periodically to evaluate the structural integrity of the safe storage enclosure and to ensure confinement of any remaining hazardous materials. "This entry marks a transition of sorts because the Hanford Long-Term Stewardship Program, for the first time, was responsible for conducting the entry and surveillance and maintenance activities," said Keith Grindstaff, Energy Department Long-Term Stewardship Program Manager. "As the River Corridor cleanup work is completed and transitioned to long-term stewardship, our program will manage any on-going requirements."

  8. F Reactor Inspection

    ScienceCinema (OSTI)

    Grindstaff, Keith; Hathaway, Boyd; Wilson, Mike

    2014-11-24T23:59:59.000Z

    Workers from Mission Support Alliance, LLC., removed the welds around the steel door of the F Reactor before stepping inside the reactor to complete its periodic inspection. This is the first time the Department of Energy (DOE) has had the reactor open since 2008. The F Reactor is one of nine reactors along the Columbia River at the Department's Hanford Site in southeastern Washington State, where environmental cleanup has been ongoing since 1989. As part of the Tri-Party Agreement, the Department completes surveillance and maintenance activities of cocooned reactors periodically to evaluate the structural integrity of the safe storage enclosure and to ensure confinement of any remaining hazardous materials. "This entry marks a transition of sorts because the Hanford Long-Term Stewardship Program, for the first time, was responsible for conducting the entry and surveillance and maintenance activities," said Keith Grindstaff, Energy Department Long-Term Stewardship Program Manager. "As the River Corridor cleanup work is completed and transitioned to long-term stewardship, our program will manage any on-going requirements."

  9. ucsf sustainability healthy environment, sustainable future

    E-Print Network [OSTI]

    Yamamoto, Keith

    ucsf sustainability healthy environment, sustainable future UC SAN FRANCISCO ANNUAL REPORT FY 2009-2010 Annual Report of the Chancellor's Advisory Committee on Sustainability #12;TABLE OF CONTENTS Executive Summary 1 UCSF Sustainability Governance 3 Table 1: CACS Members 4 Figure 1: UCSF Sustainability

  10. Partnership Efforts in the Sustainable Rangelands LORI HIDINGER

    E-Print Network [OSTI]

    Wyoming, University of

    , and through the Delphi Process. In 17 #12;Table 1: Organizations Involved in the Sustainable RangelandsPartnership Efforts in the Sustainable Rangelands Roundtable LORI HIDINGER The author is program manager, Sustainable Biosphere Initiative and Science Programs, Ecological Society of America, Washington

  11. Psychology of Sustainable Development

    E-Print Network [OSTI]

    Milfont, Taciano Lemos

    2003-01-01T23:59:59.000Z

    to achieve sustainable development: economic, environmental,out historical aspects of sustainable development and itsPsychology of Sustainable Development By Peter Schmuck and

  12. Ecosystems and Sustainable Development

    E-Print Network [OSTI]

    Tufford, Dan

    1999-01-01T23:59:59.000Z

    Review: Ecosystems and Sustainable Development Editors: J.L.Ecosystems and Sustainable Development. Southhampton, UK:as well. Ecosystems and Sustainable Development is a strong

  13. Ecosystems and Sustainable Development

    E-Print Network [OSTI]

    Tufford, Dan

    1999-01-01T23:59:59.000Z

    Ecosystems and Sustainable Development Editors: J.L. Uso,Ecosystems and Sustainable Development. Southhampton, UK:ISBN: 1-85312-502-4. Sustainable development research is a

  14. Psychology of Sustainable Development

    E-Print Network [OSTI]

    Milfont, Taciano Lemos

    2003-01-01T23:59:59.000Z

    to achieve sustainable development: economic, environmental,Psychology of Sustainable Development By Peter Schmuck andPsychology of Sustainable Development. Norwell, MA: Kluwer

  15. Active stewardship: sustainable future

    Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

    Active stewardship: sustainable future Active stewardship: sustainable future Energy sustainability is a daunting task: How do we develop top-notch innovations with some of the...

  16. Review: Hijacking Sustainability

    E-Print Network [OSTI]

    Antonelli, Monika

    2010-01-01T23:59:59.000Z

    addressing the attack on sustainability, Sharon Beder’s 2002Review: Hijacking Sustainability By Adrian Parr Reviewed byParr, Adrian. Hijacking Sustainability. Cambridge, MA: MIT

  17. Sustainability and Transport

    E-Print Network [OSTI]

    Gilbert, Richard

    2006-01-01T23:59:59.000Z

    2005. Integrating Sustainability into the Trans- portationTHOUGHT PIECE Sustainability and Transport by Richardof the concept of sustainability to transport planning. In

  18. Environmental Sustainability

    E-Print Network [OSTI]

    Energy Systems & Climate Change 21 3.2 Communication 24 #12;Prospectus for Environmental Sustainability: Distance Learning 2014-2015 3 MEEN40820 Technical Communications 24 IS40030 People Information & Communication 26 ENVB40380 Managing the Interface between Science & Policy 28 3.3 Resource Characterisation

  19. Environmental Sustainability

    E-Print Network [OSTI]

    Energy Systems & Climate Change 21 3.2 Communication 24 #12;Prospectus for Environmental Sustainability: Distance Learning 2013-2014 3 MEEN40820 Technical Communications 24 IS40030 People Information & Communication 26 ENVB40380 Managing the Interface between Science & Policy 28 3.3 Resource Characterisation

  20. Sustainablesta Sustainable

    E-Print Network [OSTI]

    Richner, Heinz

    welfare impacts associated with poor sanitation in Southeast Asia has shown that the annual per capita research related to the core issues of the region, namely (i) environmental sanitation and health, (ii of adequate environmental sanitation has been identified as one of the main issues related to sustainable

  1. Y-12 Site Sustainability Plan

    SciTech Connect (OSTI)

    Sherry, T. D.; Kohlhorst, D. P.; Little, S. K.

    2011-12-01T23:59:59.000Z

    The accomplishments to date and the long-range planning of the Y-12 Energy Management and Sustainability and Stewardship programs support the DOE and the National Nuclear Security Administration (NNSA) vision for a commitment to energy efficiency and sustainability and to achievement of the Guiding Principles. Specifically, the Y-12 vision is to support the Environment, Safety and Health Policy and the DOE Strategic Sustainability Performance Plan (SSPP) while promoting overall sustainability and reduction of greenhouse gas (GHG) emissions. Table ES.2 gives a comprehensive overview of Y-12's performance status and planned actions. B&W Y-12's Energy Management mission is to incorporate renewable energy and energy efficient technologies site-wide and to position Y-12 to meet NNSA energy requirement needs through 2025 and beyond. During FY 2011, the site formed a sustainability team (Fig. ES.1). The sustainability team provides a coordinated approach to meeting the various sustainability requirements and serves as a forum for increased communication and consistent implementation of sustainability activities at Y-12. The sustainability team serves as an information exchange mechanism to promote general awareness of sustainability information, while providing a system to document progress and to identify resources. These resources are necessary to implement activities that support the overall goals of sustainability, including reducing the use of resources and conserving energy. Additionally, the team's objectives include: (1) Foster a Y-12-wide philosophy to conserve resources; (2) Reduce the impacts of production operations in a cost-effective manner; (3) Increase materials recycling; (4) Use a minimum amount of energy and fuel; (5) Create a minimum of waste and pollution in achieving Y-12-strategic objectives; (6) Develop and implement techniques, technologies, process modifications, and programs that support sustainable acquisition; (7) Minimize the impacts to resources, including energy/fuel, water, waste, pesticides, and pollution generation; (8) Incorporate sustainable design principles into the design and construction of facility upgrades, new facilities, and infrastructure; and (9) Comply with federal and state regulations, executive orders, and DOE requirements. Y-12 is working to communicate its sustainment vision through procedural, engineering, operational, and management practices. The site will make informed decisions based on the application of the five Guiding Principles for HPSBs to the maximum extent possible.

  2. Program management plan for the Molten Salt Reactor Experiment Remediation Project at Oak Ridge National Laboratory, Oak Ridge, Tennessee

    SciTech Connect (OSTI)

    NONE

    1996-09-01T23:59:59.000Z

    The primary mission of the Molten Salt Reactor Experiment (MSRE) Remediation Project is to effectively implement the risk-reduction strategies and technical plans to stabilize and prevent further migration of uranium within the MSRE facility, remove the uranium and fuel salts from the system, and dispose of the fuel and flush salts by storage in appropriate depositories to bring the facility to a surveillance and maintenance condition before decontamination and decommissioning. This Project Management Plan (PMP) for the MSRE Remediation Project details project purpose; technical objectives, milestones, and cost objectives; work plan; work breakdown structure (WBS); schedule; management organization and responsibilities; project management performance measurement planning, and control; conduct of operations; configuration management; environmental, safety, and health compliance; quality assurance; operational readiness reviews; and training.

  3. Light Water Reactor Sustainability (LWRS) Program – Non-Destructive Evaluation (NDE) R&D Roadmap for Determining Remaining Useful Life of Aging Cables in Nuclear Power Plants

    SciTech Connect (OSTI)

    Simmons, Kevin L.; Ramuhalli, Pradeep; Brenchley, David L.; Coble, Jamie B.; Hashemian, Hash; Konnik, Robert; Ray, Sheila

    2012-09-14T23:59:59.000Z

    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. 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. The workshop was attended by 30 experts in materials, electrical engineering, U.S. Nuclear Regulatory Commission (NRC), U.S. Department of Energy (DOE) National Laboratories (Oak Ridge National Laboratory, Pacific Northwest National Laboratory, Argonne National Laboratory, and Idaho National Engineering Laboratory), NDE instrumentation development, universities, commercial NDE services and cable manufacturers, and Electric Power Research Institute (EPRI). The motivation for the R&D roadmap comes from the need to address the aging management of in-containment cables at nuclear power plants (NPPs).

  4. Light Water Reactor Sustainability (LWRS) Program – Non-Destructive Evaluation (NDE) R&D Roadmap for Determining Remaining Useful Life of Aging Cables in Nuclear Power Plants

    SciTech Connect (OSTI)

    Simmons, K.L.; Ramuhali, P.; Brenchley, D.L.; Coble, J.B.; Hashemian, H.M.; Konnick, R.; Ray, S.

    2012-09-01T23:59:59.000Z

    Executive Summary [partial] 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. The workshop was attended by 30 experts in materials, electrical engineering, and NDE instrumentation development from the U.S. Nuclear Regulatory Commission (NRC), U.S. Department of Energy (DOE) National Laboratories (Oak Ridge National Laboratory, Pacific Northwest National Laboratory, Argonne National Laboratory, and Idaho National Engineering Laboratory), universities, commercial NDE service vendors and cable manufacturers, and the Electric Power Research Institute (EPRI).

  5. Sustainability Program Assistant Brandon Trelstad

    E-Print Network [OSTI]

    Escher, Christine

    Inventory #12;#12;ACKNOWLEDGEMENTS #12;Acknowledgments Due to the broad scope of this inventory, a large number of people from many, Corvallis: Tony Fuerte - First Student: Brian Maxwell - Carson Oil: Gena Conner Government Organizations

  6. Sustainability Published December 2009

    E-Print Network [OSTI]

    Bandettini, Peter A.

    Sustainability Report Published December 2009 #12;#12;NIEHS Sustainability Report #12;#12;Table........................................................................................................9 Managing for Sustainability....................................................................................................45 #12;A Message from Our Director In order to sustain and improve life on Earth, we must

  7. ASSESSMENT OF DEGRADATION OF EQUIPMENT AND MATERIALS IN RELATION TO SUSTAINABILITY MEASURES

    E-Print Network [OSTI]

    Magnuson, George Raynor

    2013-12-31T23:59:59.000Z

    Sustainability is the one of the newest design considerations in building construction. Current programs of sustainability such as Energy Star for buildings and LEED, are providing methods to reduce operational energy use and encourage sustainable...

  8. Implementing and Sustaining Operator Led Energy Efficiency Improvements

    E-Print Network [OSTI]

    Hoyle, A.; Knight, N.; Rutkowski, M.

    2011-01-01T23:59:59.000Z

    , to significantly reduce energy consumption, the site must focus on a strategic approach which involves developing, implementing and sustaining a client specific program of energy optimization. We discuss ways of sustaining energy performance through operator led...

  9. Sustainable Developments PhotograPhbybrucegilbert/earthinstitute;illustrationbyMattcollins

    E-Print Network [OSTI]

    , and research and development, especially sustain- able energy--all areas where the U.S. lags discernibly behind government is launching several much needed programs in education, health, energy and infrastructureOPINION Sustainable Developments Photogra

  10. A program toward a fusion reactor* P.-H. Rebut,+ M. L. Watkins, D. J. Gambier, and D. Boucher

    E-Print Network [OSTI]

    between the model and JET data. The main predictions are also consistent with statistical scaling laws without a significant increase in world funding. I. INTRODUCTION Present fusion research programs out the main results achieved in JET. Furthermore, a clearer picture of energy and particle transport

  11. Using mixed integer programming to schedule experiments on the Texas A&M University nuclear science center reactor

    E-Print Network [OSTI]

    Drees, Lawrence David

    1999-01-01T23:59:59.000Z

    have only due-dates. Some jobs require tooling, while others do not. This problem is modeled as a time-indexed Mixed Integer Program. Constraints were formed and variables were defined in such a way to minimize-to the fullest extent possible-the number...

  12. DOE Sustainability SPOtlight

    Broader source: Energy.gov [DOE]

    Newsletter highlights the recipients of the U.S. Department of Energy (DOE) Sustainability Performance Office (SPO) 2014 Sustainability Awards.

  13. Interagency Sustainability Working Group

    Broader source: Energy.gov [DOE]

    The Interagency Sustainability Working Group (ISWG) is the coordinating body for sustainable buildings in the federal government.

  14. Sustainable NREL

    ScienceCinema (OSTI)

    None

    2013-05-29T23:59:59.000Z

    The National Renewable Energy Laboratory prides itself on not only advancing the renewable energy, but "walking the talk" when it comes to sustainable practices. "When you look at our laboratories, you will see energy efficiency in action, but you'll also see renewable energy. We walk the walk and we talk the talk. We believe in it and we want to live it also."

  15. Sustainable NREL

    SciTech Connect (OSTI)

    None

    2011-01-01T23:59:59.000Z

    The National Renewable Energy Laboratory prides itself on not only advancing the renewable energy, but "walking the talk" when it comes to sustainable practices. "When you look at our laboratories, you will see energy efficiency in action, but you'll also see renewable energy. We walk the walk and we talk the talk. We believe in it and we want to live it also."

  16. Advanced Reactor Thermal Hydraulic Modeling | Argonne Leadership...

    Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

    Advanced Reactor Thermal Hydraulic Modeling PI Name: Paul Fischer PI Email: fischer@mcs.anl.gov Institution: Argonne National Laboratory Allocation Program: INCITE Allocation Hours...

  17. Operation of a steam hydro-gasifier in a fluidized bed reactor

    E-Print Network [OSTI]

    Park, Chan Seung; Norbeck, Joseph N.

    2008-01-01T23:59:59.000Z

    Using Self-Sustained Hydro- Gasification." [0011] In aprocess, using a steam hydro-gasification reactor (SHR) thepyrolysis and hydro-gasification in a single step. This

  18. E-Print Network 3.0 - army gas-cooled reactor Sample Search Results

    Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

    ENABLING SUSTAINABLE NUCLEAR POWER Summary: and NRE Design Class., "Advances in the Subcritical, Gas-Cooled Fast Transmutation Reactor Concept", Nucl... . Tedder, J. Lackey, J....

  19. Reactor physics project final report

    E-Print Network [OSTI]

    Driscoll, Michael J.

    1970-01-01T23:59:59.000Z

    This is the final report in an experimental and theoretical program to develop and apply single- and few-element methods for the determination of reactor lattice parameters. The period covered by the report is January 1, ...

  20. Interdisciplinary Perspectives on Sustainability Sustainability 300

    E-Print Network [OSTI]

    D'Orsogna, Maria Rita

    will build skills to apply theories to real- world problems of sustainability, and develop the ability1 Interdisciplinary Perspectives on Sustainability Sustainability 300 Fall 2014 Class: 19301 Room and Sustainability loraine.lundquist@csun.edu JR 219B Course Description This course uses an interdisciplinary

  1. sustainability and u} Sustainability at the

    E-Print Network [OSTI]

    Webb, Peter

    sustainability and u} #12;Sustainability at the University of Minnesota is a continuous effort. The University of Minnesota is committed to incorporating sustainability into its teaching, research and outreach and the operations that support them. sustainability} From groundbreaking research to unique recycling options

  2. Assessment of University Sustainability Activities SUSTAINABILITY TRACKING,

    E-Print Network [OSTI]

    Dodla, Ramana

    Assessment of University Sustainability Activities under the SUSTAINABILITY TRACKING, ASSESSMENT Rashed-Ali, PhD. Prepared for: The UTSA Sustainability Council May 3rd , 2011 #12;yhd/s ^hDD Zz 2 | P a g-Ali, Assistant Professor in the College of Architecture, conducted a survey and assessment of UTSA sustainability

  3. Cultivating Sustainable Coffee: Persistent Paradoxes

    E-Print Network [OSTI]

    Bacon, Christopher M.; Mendez, Ernesto; Fox, Jonathan A

    2008-01-01T23:59:59.000Z

    survival and sustainable development processes will dependinclusive and sustainable rural development processes. Ininclusive sustainable rural devel- opment process (Miranda

  4. Achieving Sustainability Cindy Carlsson

    E-Print Network [OSTI]

    Minnesota, University of

    Achieving Sustainability at MnDOT Cindy Carlsson MnDOT Office of Policy Analysis, Research and Innovation 22nd Annual Transportation Research Conference May 24, 2011 #12;Sustainable practices respect Sustainability #12;Environmental Sustainability Sustainable practices ¡ Are compatible with and may enhance

  5. Sustainability Cal State Fullerton

    E-Print Network [OSTI]

    de Lijser, Peter

    Sustainability at Cal State Fullerton A Report from the Sustainability Initiative Study Group October 28, 2008 #12;Sustainability at Cal State Fullerton A Report from the Sustainability Initiative Safety Sally Yassine Contracts & Procurement #12;Sustainability at Cal State Fullerton A Report from

  6. Sustainable Furman NOVEMBER 2009

    E-Print Network [OSTI]

    and destination taking the long view #12;SUSTAINABLE FURMAN 1 EXECUTIVE SUMMARY Living sustainably entails takingSustainable Furman #12;NOVEMBER 2009 sustainability meeting humanity's needs journey in perpetuity, a commitment to sustainability promotes the well-being of people and campuses over the long term

  7. Sustainable Procurement Policy

    E-Print Network [OSTI]

    Burton, Geoffrey R.

    Sustainable Procurement Policy #12;2 Sustainable Procurement What is sustainable procurement? "Sustainable procurement is a process whereby organisations meet their needs for goods, services, works to the environment" Procuring the Future (Sustainable Procurement Task Force June 2006) Why is it important

  8. Sustainable Energy Resources for Consumers Webinar on Residential...

    Broader source: Energy.gov (indexed) [DOE]

    Publications Sustainable Energy Resources for Consumers (SERC) - GeothermalGround-Source Heat Pumps Residential Retrofit Program Design Guide Overview Transcript.doc Residential...

  9. Sustainable Energy Resources for Consumers (SERC) Vermont Highlight...

    Broader source: Energy.gov (indexed) [DOE]

    on Vermont's innovative strategy for helping low-income families save energy through its Sustainable Energy Resources for Consumers (SERC) program. sercvthighlight.pdf More...

  10. Algae: The Source of Reliable, Scalable, and Sustainable Liquid...

    Office of Energy Efficiency and Renewable Energy (EERE) Indexed Site

    Scalable, and Sustainable Liquid Transportation Fuels At the February 12, 2009 joint Web conference of DOE's Biomass and Clean Cities programs, Brian Goodall (Sapphire Energy)...

  11. Societal health and urban sustainability indicators

    SciTech Connect (OSTI)

    Petrich, C.H.; Tonn, B.E.

    1996-08-27T23:59:59.000Z

    Without the social will, no city can successfully Undertake the planning and programs necessary for meaningful progress toward sustainability. Social will derives from wellsprings of vital societal health. This paper presents an approach to helping cities in APEC member economies initiate a program for developing indicators of sustainability. Representative indicators of social capital and other aspects of civic engagement, as proxies for societal health, are presented.

  12. James P. Mosquera Director, Reactor Plant Components

    E-Print Network [OSTI]

    of the application of nuclear reactor power to capital ships of the U.S. Navy, and other assigned projects. Mr for steam generator technology (within the Nuclear Components Division); and power plant systems engineer working for the U.S. Naval Nuclear Propulsion Program (a.k.a. Naval Reactors). This program is a joint

  13. "Leadership for Sustainable

    E-Print Network [OSTI]

    Saskatchewan, University of

    ! 1! ! ! "Leadership for Sustainable Development in Commonwealth Africa" 8th !Forum! Commonwealth! Secretariat! #12;! 2! Ethical Leadership for Sustainable Development Background Paper prepared! Executive Summary The "Ethical Leadership for Sustainable Development" paper offers Heads of Public Service

  14. CENTER FOR SUSTAINABCENTER FOR SUSTAINABLE TOURISMLE TOURISM ANNUAL REPORT

    E-Print Network [OSTI]

    CENTER FOR SUSTAINABCENTER FOR SUSTAINABLE TOURISMLE TOURISM ANNUAL REPORT JULY 1, 2012­JUNE 30 Long 4 Center for Sustainable Tourism Overview 5 Center Faculty and Staff / Oliver Named Graduate Program Director 6 Master of Science in Sustainable Tourism 2013 Graduates / MS-ST Faculty Graduate

  15. Nanocellulose A sustainable nanomaterial derived from wood pulp with

    E-Print Network [OSTI]

    Thompson, Michael

    Nanocellulose A sustainable nanomaterial derived from wood pulp with applications in composites, sensors, and biomedical devices. The Sustainable Nano-Biocomposites lab in the chemical engineering-renewable resources while offering better performance. #12;Research Program Research in the Sustainable Nano

  16. Integrated Renewable Energy and Campus Sustainability Initiative

    SciTech Connect (OSTI)

    Uthoff, Jay; Jensen, Jon; Bailey, Andrew

    2013-09-25T23:59:59.000Z

    Renewable energy, energy conservation, and other sustainability initiatives have long been a central focus of Luther College. The DOE funded Integrated Renewable Energy and Campus Sustainability Initiative project has helped accelerate the College’s progress toward carbon neutrality. DOE funds, in conjunction with institutional matching funds, were used to fund energy conservation projects, a renewable energy project, and an energy and waste education program aimed at all campus constituents. The energy and waste education program provides Luther students with ideas about sustainability and conservation guidelines that they carry with them into their future communities.

  17. Materials Science and Technology Division Light-Water-Reactor Safety Research Program. Quarterly progress report, April-June 1983. Volume 2

    SciTech Connect (OSTI)

    Shack, W.J.

    1984-06-01T23:59:59.000Z

    The progress report summarizes the Argonne National Laboratory work performed during April, May, and June 1983 on water reactor safety problems. The research and development areas covered are Environmentally Assisted Cracking in Light Water Reactors, Transient Fuel Response and Fission Product Release, Clad Properties for Code Verification, and Long-Term Embrittlement of Cast Duplex Stainless Steels in LWR Systems.

  18. Materials Science and Technology Division light-water-reactor safety research program. Quarterly progress report, July-September 1983. Volume 3

    SciTech Connect (OSTI)

    Not Available

    1984-07-01T23:59:59.000Z

    This progress report summarizes the Argonne National Laboratory work performed during July, August, and September 1983 on water reactor safety problems. The research and development areas covered are Environmentally Assisted Cracking in Light Water Reactors (reported elsewhere), Transient Fuel Response and Fission Product Release, Clad Properties for Code Verification, and Long-Term Embrittlement of Cast Duplex Stainless Steels in LWR Systems (reported elsewhere).

  19. Living a Sustainable Future

    Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

    solve the energy crisis through biological methods, including genetically engineering algae and cyanobacteria. Create a Sustainable Future: Living Living a Sustainable Future How...

  20. Sustainability Bulletin USGBC Sustainable Speaker Series

    E-Print Network [OSTI]

    Kidd, William S. F.

    series of events recognizing Earth Day and the need to increase sustainable living on campus. This yearMay 2014 Sustainability Bulletin #12;USGBC Sustainable Speaker Series May 13 Give and Go May 13th themselves from many of the technology devices that have become ubiquitous in our daily lives, and to start

  1. SUSTAINABILITY OPPORTUNITY Waste audits from campus buildings reveal that 30% of the trash Stanford sends to the landfill is

    E-Print Network [OSTI]

    Straight, Aaron

    How To... SUSTAINABILITY OPPORTUNITY Waste audits from campus buildings reveal that 30 on campus have active composting programs. Interested buildings and departments can start a voluntary office;MORE INFORMATION SUSTAINABLE STANFORD'S WASTE REDUCTION EFFORTS http://sustainable

  2. Nuclear Energy Research Initiative (NERI) Program Continuous Fiber Wound Ceramic Composite (CFCC) for Commercial Water Reactor Fuel-Technical Progress Report

    SciTech Connect (OSTI)

    Feinroth, Herbert

    2000-01-01T23:59:59.000Z

    Our program began on August 1, 1999. As of January 1, 2000, the progress has been in contracting, materials selection, and test planning. All 3 subcontracts are now in place (McDermott Technologies Inc. for ceramic fabrication, Swales Aerospace for LOCA testing, and Massachusetts Institute of Technology for in Reactor testing). With regard to material selection, we visited McDermott Technologies on December 6, 1999 to discuss the progress on Materials Selection and issues regarding Permeability Reduction in CFCC materials. We are evaluating several options for reducing the permeability of the CFCC materials, including Chemical Vapor Infiltration. McDermott Technologies is approximately two months late on their scheduled delivery to Gamma of Materials Selection reports. They have indicated by letter that they plan to deliver a draft and then final Materials Selection Report to Gamma by January 15 and February 1st, 2000, respectively. With regard to Test Planning, Swales Aerospace is proceeding with engineering the test chamber. The power supply selection for the Kanthal furnace was changed from AC to DC current to simplify equipment and operation. The mechanism for opening the ''sliding door'' on bottom of furnace has been changed from air cylinder to stainless steel spring/cord to provide inherent simplicity and failsafe operation. Alumina tubing for apparatus calibration was obtained from Coors Ceramics; 0.5 x 1/16 foot wall x 16 inches, grade AD-998, 99.8% Al{sub 2}O{sub 3}, density 3.9 gr/cc. This will be cut into 3 inch specimen and very closely matches the expected test specimens from McDermott. Swales and Gamma are currently selecting extension springs from Associated Spring to provide a tension on furnace ''bottom door''. Swales and Gamma are currently evaluating sample of Alumina board from Zircar for the furnace ''door.''

  3. Risk-informed design guidance for a Generation-IV gas-cooled fast reactor emergency core cooling system

    E-Print Network [OSTI]

    Delaney, Michael J. (Michael James), 1979-

    2004-01-01T23:59:59.000Z

    Fundamental objectives of sustainability, economics, safety and reliability, and proliferation resistance, physical protection and stakeholder relations must be considered during the design of an advanced reactor. However, ...

  4. Sustainable Development and Sustainable Transportation: Strategies for Economic Prosperity, Environmental Quality, and Equity

    E-Print Network [OSTI]

    Deakin, Elizabeth

    2001-01-01T23:59:59.000Z

    03 Sustainable Development and Sustainable Transportation:17 Sustainable Development and Sustainable Transportation:Wimsatt, Alma. “Sustainable Development and International

  5. Sustainable Development & Sustainable Transportation: Strategies for Economic Prosperity, Environmental Quality, and Equity

    E-Print Network [OSTI]

    Deakin, Elizabeth

    2001-01-01T23:59:59.000Z

    03 Sustainable Development and Sustainable Transportation:17 Sustainable Development and Sustainable Transportation:Wimsatt, Alma. “Sustainable Development and International

  6. Sustainable Development Summer Intern Report 2013 Sustainable Development Summer Intern

    E-Print Network [OSTI]

    Sustainable Development Summer Intern Report 2013 Sustainable Development Summer Intern Final amongst university's invested in sustainable development. Our small but mighty size allows us to build through positive sustainable practices. As the Sustainable Development Summer Intern I am fortunate enough

  7. Russell Ranch Sustainable Agriculture Facility Agricultural Sustainability Institute

    E-Print Network [OSTI]

    California at Davis, University of

    Russell Ranch Sustainable Agriculture Facility Agricultural Sustainability Institute College of Agricultural Sustainability Institute Professor, Department of LAWR With input from Steve Kaffka, Ford Denison Sustainability Institute The Russell Ranch Sustainable Agriculture Facility is a unique 300-acre facility near

  8. DOE Technical Assistance Program

    Broader source: Energy.gov (indexed) [DOE]

    Provide SEP & EECBG recipients with resources needed to swiftly implement successful and sustainable clean energy programs. Objectives: To provide proactive assistance, technical...

  9. Community Innovations Grant Program

    Broader source: Energy.gov [DOE]

    The Community Innovations Grants Program provides funding for communities to increase voluntary support for clean energy and to build model sustainable communities.

  10. Nuclear power reactor education and training at the Ford nuclear reactor

    SciTech Connect (OSTI)

    Burn, R.R.

    1989-01-01T23:59:59.000Z

    Since 1977, staff members of the University of Michigan's Ford nuclear reactor have provided courses and reactor laboratory training programs for reactor operators, engineers, and technicians from seven electric utilities, including Cleveland Electric Illuminating, Consumers Power, Detroit Edison, Indiana and Michigan Electric, Nebraska Public Power, Texas Utilities Generating Company, and Toledo Edison. Reactor laboratories, instrument technician training, and reactor physics courses have been conducted at the university. Courses conducted at plant sites include reactor physics, thermal sciences, materials sciences, and health physics and radiation protection.

  11. Fast reactors and nuclear nonproliferation

    SciTech Connect (OSTI)

    Avrorin, E.N. [Russian Federal Nuclear Center - Zababakhin Institute of Applied Physics, Snezhinsk (Russian Federation); Rachkov, V.I.; Chebeskov, A.N. [State Scientific Center of the Russian Federation - Institute for Physics and Power Engineering, Bondarenko Square, 1, Obninsk, Kaluga region, 249033 (Russian Federation)

    2013-07-01T23:59:59.000Z

    Problems are discussed with regard to nuclear fuel cycle resistance in fast reactors to nuclear proliferation risk due to the potential for use in military programs of the knowledge, technologies and materials gained from peaceful nuclear power applications. Advantages are addressed for fast reactors in the creation of a more reliable mode of nonproliferation in the closed nuclear fuel cycle in comparison with the existing fully open and partially closed fuel cycles of thermal reactors. Advantages and shortcomings are also discussed from the point of view of nonproliferation from the start with fast reactors using plutonium of thermal reactor spent fuel and enriched uranium fuel to the gradual transition using their own plutonium as fuel. (authors)

  12. Framework for Measuring Sustainable

    E-Print Network [OSTI]

    Levinson, David M.

    Knight Foundation will use this sustainability framework for internal organizational purposes with the possibility

  13. Sustainable Nanomaterials Industry Perspective

    Broader source: Energy.gov [DOE]

    Presentation for the Sustainable Nanomaterials Workshop by MeadWestvaco Corporation held on June 26, 2012

  14. Measuring Energy Sustainability

    E-Print Network [OSTI]

    20 Measuring Energy Sustainability David L. Greene Abstract For the purpose of measurement, energy sustainability is defined as ensuring that future generations have energy resources that enable them to achieve that there are valid, more comprehensive understandings of sustainability and that energy sustainability as de- fined

  15. Sustainability in colleges 15

    E-Print Network [OSTI]

    Melham, Tom

    Sustainability in colleges 15 Carbon reduction 5 Water 7 Travel8 Waste,recyclingandreuse10 Sustainability Report 2011/2012 #12;2University of Oxford Environmental Sustainability Report 2011/12 "As Chair of the Sustainability Steering Group, I have seen a significant shift in staff and students' expectations

  16. UC Sustainability Office Report

    E-Print Network [OSTI]

    Hickman, Mark

    UC Sustainability Office Report Introduction Welcome to the third annual UC Sustainability Office infrastructure, UC is now trending in a positive direction against some sustainability indicators. Electricity products and membership of the UC Sustainability Community is growing. There are concerns around the amount

  17. Achieving Sustainability Cindy Carlsson

    E-Print Network [OSTI]

    Minnesota, University of

    Achieving Sustainability Cindy Carlsson Mn/DOT Office of Policy Analysis, Research and Innovation April 21, 2011 #12;Sustainability Is Not New Mn/DOT has long been a leader in CSS and environmental excellence. . . . . . so we're well along on the path to sustainability! #12;Today Sustainability is More

  18. Progress Report 2014 Sustainability

    E-Print Network [OSTI]

    Y Yale Progress Report 2014 Sustainability Strategic Plan #12;President Salovey announced Yale's continued commitment to sustainability when he released the University's second Sustainability Strategic-going efforts to address sustainability and called upon students, faculty, and staff to play an active role

  19. Sustainability Commitments Commitment

    E-Print Network [OSTI]

    Heller, Barbara

    : On a fully sustainable urban campus, campus buildings become a living example of environmental researchSustainability Commitments Emissions Commitment: On a fully sustainable urban campus, the materials for elimination. Supply Chain/Waste Management Commitment: On a fully sustainable urban campus, material flows

  20. Sustainable Rangelands Roundtable Overview

    E-Print Network [OSTI]

    Wyoming, University of

    Sustainable Rangelands Roundtable Overview Kristie Maczko, PhD John Tanaka, PhD http://SustainableRangelands.org #12;Overview Sustainable Rangelands Roundtable (SRR) background, products and current projects Introduction to criteria and indicators #12;Sustainable Rangelands Roundtable Is a collaborative partnership

  1. VISIONS FOR A SUSTAINABLE

    E-Print Network [OSTI]

    Riesenhuber, Maximilian

    THE VISIONS FOR A SUSTAINABLE GEORGETOWN INITIATIVE study with recommendations for a campus climate action plan prepared for the Hoyas Roundtable on Sustainability MARCH 15, 2012 THE HOYA ROUNDTABLE SERIES: SPOTLIGHT ON SUSTAINABILITY GEORGETOWN SUSTAINABILITY #12;Georgetown University is taking major steps toward

  2. ASSET Minor Sustainable

    E-Print Network [OSTI]

    ASSET Minor Sustainable Design Engineering Sustainable Science, Engineering and Technology (ASSET a sustainable world as a complex, multidisciplinary challenge. This minor will help you understand this thinking especially for this purpose. ¡ You'll learn how to enact successful strategies for dealing with sustainable

  3. The National Hydropower Asset Assessment Program (NHAAP) is an integrated energy, water, and ecosystem research effort for sustainable hydroelectricity generation and water management. The NHAAP conducts research on new

    E-Print Network [OSTI]

    , and ecosystem research effort for sustainable hydroelectricity generation and water management. The NHAAP

  4. Materials Science and Technology Division Light-Water-Reactor Safety Research Program. Volume 4. Quarterly progress report, October-December 1983

    SciTech Connect (OSTI)

    Not Available

    1984-08-01T23:59:59.000Z

    The research and development areas covered are Environmentally Assisted Cracking in Light Water Reactors, Transient Fuel Response and Fission Product Release, Clad Properties for Code Verification, and Long-Term Embrittlement of Cast Duplex Stainless Steels in LWR Systems.

  5. MAPPING FLOW LOCALIZATION PROCESSES IN DEFORMATION OF IRRADIATED REACTOR STRUCTURAL ALLOYS - FINAL REPORT. Nuclear Energy Research Initiative Program No. MSF99-0072. Period: August 1999 through September 2002. (ORNL/TM-2003/63)

    SciTech Connect (OSTI)

    Farrell, K.

    2003-09-26T23:59:59.000Z

    Metals that can sustain plastic deformation homogeneously throughout their bulk tend to be tough and malleable. Often, however, if a metal has been hardened it will no longer deform uniformly. Instead, the deformation occurs in narrow bands on a microscopic scale wherein stresses and strains become concentrated in localized zones. This strain localization degrades the mechanical properties of the metal by causing premature plastic instability failure or by inducing the formation of cracks. Irradiation with neutrons hardens a metal and makes it more prone to deformation by strain localization. Although this has been known since the earliest days of radiation damage studies, a full measure of the connection between neutron irradiation hardening and strain localization is wanting, particularly in commercial alloys used in the construction of nuclear reactors. Therefore, the goal of this project is to systematically map the extent of involvement of strain localization processes in plastic deformation of three reactor alloys that have been neutron irradiated. The deformation processes are to be identified and related to changes in the tensile properties of the alloys as functions of neutron fluence (dose) and degree of plastic strain. The intent is to define the role of strain localization in radiation embrittlement phenomena. The three test materials are a tempered bainitic A533B steel, representing reactor pressure vessel steel, an annealed 316 stainless steel and annealed Zircaloy-4 representing reactor internal components. These three alloys cover the range of crystal structures usually encountered in structural alloys, i.e. body-centered cubic (bcc), face-centered cubic (fcc), and close-packed hexagonal (cph), respectively. The experiments were conducted in three Phases, corresponding to the three years duration of the project. Phases 1 and 2 addressed irradiations and tensile tests made at near-ambient temperatures, and covered a wide range of neutron fluences. Phase 3 was aimed at a higher irradiation and test temperature of about 288 C, pertinent to the operating temperature of commercial reactor pressure vessel steels. Phase 3 explored a narrower fluence range than Phases 1 and 2, and it included an investigation of the strain rate dependence of deformation.

  6. Sustainable Acquisition Coding System | Department of Energy

    Broader source: Energy.gov (indexed) [DOE]

    Sustainable Acquisition Coding System Sustainable Acquisition Coding System Sustainable Acquisition Coding System Sustainable Acquisition Coding System More Documents &...

  7. Science and technology for a sustainable energy future: Accomplishments of the Energy Efficiency and Renewable Energy Program at Oak Ridge National Laboratory

    SciTech Connect (OSTI)

    Brown, M.A.; Vaughan, K.H.

    1995-03-01T23:59:59.000Z

    Accomplishments of the Energy Efficiency and Renewable Energy Program at the Oak Ridge National Laboratory are presented. Included are activities performed in the utilities, transportation, industrial, and buildings technology areas.

  8. Nuclear reactor engineering

    SciTech Connect (OSTI)

    Glasstone, S.; Sesonske, A.

    1981-01-01T23:59:59.000Z

    Chapters are presented concerning energy from nuclear fission; nuclear reactions and radiations; diffusion and slowing-down of neutrons; principles of reactor analysis; nuclear reactor kinetics and control; energy removal; non-fuel reactor materials; the reactor fuel system; radiation protection and environmental effects; nuclear reactor shielding; nuclear reactor safety; and power reactor systems.

  9. The Sustainability of Sustainable Energy

    Broader source: Energy.gov (indexed) [DOE]

    AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE:1 First Use of Energy for All Purposes (Fuel and Nonfuel),Feet) Year Jan Feb Mar Apr May Jun Jul(Summary) "ofEarlyEnergyDepartment of EnergyProgram (Alabama)Technology fortosummariesTheU.S. DepartmentThe

  10. Hopi Sustainable Energy Plan

    SciTech Connect (OSTI)

    Norman Honie, Jr.; Margie Schaff; Mark Hannifan

    2004-08-01T23:59:59.000Z

    The Hopi Tribal Government as part of an initiative to ?Regulate the delivery of energy and energy services to the Hopi Reservation and to create a strategic business plan for tribal provision of appropriate utility, both in a manner that improves the reliability and cost efficiency of such services,? established the Hopi Clean Air Partnership Project (HCAPP) to support the Tribe?s economic development goals, which is sensitive to the needs and ways of the Hopi people. The Department of Energy (DOE) funded, Formation of Hopi Sustainable Energy Program results are included in the Clean Air Partnership Report. One of the Hopi Tribe?s primary strategies to improving the reliability and cost efficiency of energy services on the Reservation and to creating alternative (to coal) economic development opportunities is to form and begin implementation of the Hopi Sustainable Energy Program. The Hopi Tribe through the implementation of this grant identified various economic opportunities available from renewable energy resources. However, in order to take advantage of those opportunities, capacity building of tribal staff is essential in order for the Tribe to develop and manage its renewable energy resources. As Arizona public utilities such as APS?s renewable energy portfolio increases the demand for renewable power will increase. The Hopi Tribe would be in a good position to provide a percentage of the power through wind energy. It is equally important that the Hopi Tribe begin a dialogue with APS and NTUA to purchase the 69Kv transmission on Hopi and begin looking into financing options to purchase the line.

  11. Research reactors - an overview

    SciTech Connect (OSTI)

    West, C.D.

    1997-03-01T23:59:59.000Z

    A broad overview of different types of research and type reactors is provided in this paper. Reactor designs and operating conditions are briefly described for four reactors. The reactor types described include swimming pool reactors, the High Flux Isotope Reactor, the Mark I TRIGA reactor, and the Advanced Neutron Source reactor. Emphasis in the descriptions is placed on safety-related features of the reactors. 7 refs., 7 figs., 2 tabs.

  12. Sustainability of Tourism in Bhutan

    E-Print Network [OSTI]

    Dorji, Tandi

    2001-01-01T23:59:59.000Z

    , ornithology, Sustainability of Tourism 93 botany, white water rafting. Related to product development there is a need for more emphasis on a classification system for tourism facilities and specification of minimum standards. Marketing Strategies... to boost the local economy. The programme aims to promote the development of alternative energy, eco-tourism, conservation and education programs, Black-Necked Crane research, and monitoring and development of infrastructure for ecotourism...

  13. SPIN (Version 3. 83): A Fortran program for modeling one-dimensional rotating-disk/stagnation-flow chemical vapor deposition reactors

    SciTech Connect (OSTI)

    Coltrin, M.E. (Sandia National Labs., Albuquerque, NM (United States)); Kee, R.J.; Evans, G.H.; Meeks, E.; Rupley, F.M.; Grcar, J.F. (Sandia National Labs., Livermore, CA (United States))

    1991-08-01T23:59:59.000Z

    In rotating-disk reactor a heated substrate spins (at typical speeds of 1000 rpm or more) in an enclosure through which the reactants flow. The rotating disk geometry has the important property that in certain operating regimes{sup 1} the species and temperature gradients normal to the disk are equal everywhere on the disk. Thus, such a configuration has great potential for highly uniform chemical vapor deposition (CVD),{sup 2--5} and indeed commercial rotating-disk CVD reactors are now available. In certain operating regimes, the equations describing the complex three-dimensional spiral fluid motion can be solved by a separation-of-variables transformation{sup 5,6} that reduces the equations to a system of ordinary differential equations. Strictly speaking, the transformation is only valid for an unconfined infinite-radius disk and buoyancy-free flow. Furthermore, only some boundary conditions are consistent with the transformation (e.g., temperature, gas-phase composition, and approach velocity all specified to be independent of radius at some distances above the disk). Fortunately, however, the transformed equations will provide a very good practical approximation to the flow in a finite-radius reactor over a large fraction of the disk (up to {approximately}90% of the disk radius) when the reactor operating parameters are properly chosen, i.e, high rotation rates. In the limit of zero rotation rate, the rotating disk flow reduces to a stagnation-point flow, for which a similar separation-of-variables transformation is also available. Such flow configurations ( pedestal reactors'') also find use in CVD reactors. In this report we describe a model formulation and mathematical analysis of rotating-disk and stagnation-point CVD reactors. Then we apply the analysis to a compute code called SPIN and describe its implementation and use. 31 refs., 4 figs.

  14. SUSTAINABLE A university for sustainable development

    E-Print Network [OSTI]

    Johannesson, Henrik

    carbon offset. Additional areas of action include research and education, collaboration and communication scientifically peer-reviewed articles on sustainable development were published. ¡ Carbon dioxide emissions from

  15. Steady-state spheromak reactor studies

    SciTech Connect (OSTI)

    Krakowski, R.A.; Hagenson, R.L.

    1985-01-01T23:59:59.000Z

    After summarizing the essential elements of a gun-sustained spheromak, the potential for a steady-state is explored by means of a comprehensive physics/engineering/costing model. A range of cost-optimized reactor design points is presented, and the sensitivity of cost to key physics, engineering, and operational variables is reported.

  16. CRC handbook of nuclear reactors calculations. Vol. II

    SciTech Connect (OSTI)

    Ronen, Y.

    1986-01-01T23:59:59.000Z

    This handbook breaks down the complex field of nuclear reactor calculations into major steps. Each step presents a detailed analysis of the problems to be solved, the parameters involved, and the elaborate computer programs developed to perform the calculations. This book bridges the gap between nuclear reactor theory and the implementation of that theory, including the problems to be encountered and the level of confidence that should be given to the methods described. Volume II: Monte Carlo Calculations for Nuclear Reactors. In-Core Management of Four Reactor Types. In-Core Management in CANDU-PHW Reactors. Reactor Dynamics. The Theory of Neutron Leakage in Reactor Lattices. Index.

  17. RERTR program

    SciTech Connect (OSTI)

    Travelli, A. [Argonne National Lab., IL (United States)

    1997-12-01T23:59:59.000Z

    The Reduced Enrichment Research and Test Reactor (RERTR) Program was established in 1978 at the Argonne National Laboratory by the U.S. Department of Energy (DOE), which continues to fund the program and to manage it in coordination with the U.S. Department of State, the Arms Control and Disarmament Agency, and the U.S. Nuclear Regulatory Commission (NRC). The primary objective of the program is to develop the technology needed to use low-enrichment uranium (LEU) instead of high-enrichment uranium (HEU) in research and test reactors, without significant penalties in experiment performance, economics, or safety. Eliminating the continuing need of HEU supplies for research and test reactors has long been an integral part of U.S. nonproliferation policy. This paper reviews the main accomplishments of the program through the years.

  18. Nuclear Reactors and Technology

    SciTech Connect (OSTI)

    Cason, D.L.; Hicks, S.C. [eds.

    1992-01-01T23:59:59.000Z

    This publication Nuclear Reactors and Technology (NRT) announces on a monthly basis the current worldwide information available from the open literature on nuclear reactors and technology, including all aspects of power reactors, components and accessories, fuel elements, control systems, and materials. This publication contains the abstracts of DOE reports, journal articles, conference papers, patents, theses, and monographs added to the Energy Science and Technology Database during the past month. Also included are US information obtained through acquisition programs or interagency agreements and international information obtained through the International Energy Agency`s Energy Technology Data Exchange or government-to-government agreements. The digests in NRT and other citations to information on nuclear reactors back to 1948 are available for online searching and retrieval on the Energy Science and Technology Database and Nuclear Science Abstracts (NSA) database. Current information, added daily to the Energy Science and Technology Database, is available to DOE and its contractors through the DOE Integrated Technical Information System. Customized profiles can be developed to provide current information to meet each user`s needs.

  19. Catalytic reactor

    DOE Patents [OSTI]

    Aaron, Timothy Mark (East Amherst, NY); Shah, Minish Mahendra (East Amherst, NY); Jibb, Richard John (Amherst, NY)

    2009-03-10T23:59:59.000Z

    A catalytic reactor is provided with one or more reaction zones each formed of set(s) of reaction tubes containing a catalyst to promote chemical reaction within a feed stream. The reaction tubes are of helical configuration and are arranged in a substantially coaxial relationship to form a coil-like structure. Heat exchangers and steam generators can be formed by similar tube arrangements. In such manner, the reaction zone(s) and hence, the reactor is compact and the pressure drop through components is minimized. The resultant compact form has improved heat transfer characteristics and is far easier to thermally insulate than prior art compact reactor designs. Various chemical reactions are contemplated within such coil-like structures such that as steam methane reforming followed by water-gas shift. The coil-like structures can be housed within annular chambers of a cylindrical housing that also provide flow paths for various heat exchange fluids to heat and cool components.

  20. Bioconversion reactor

    DOE Patents [OSTI]

    McCarty, Perry L. (Stanford, CA); Bachmann, Andre (Palo Alto, CA)

    1992-01-01T23:59:59.000Z

    A bioconversion reactor for the anaerobic fermentation of organic material. The bioconversion reactor comprises a shell enclosing a predetermined volume, an inlet port through which a liquid stream containing organic materials enters the shell, and an outlet port through which the stream exits the shell. A series of vertical and spaced-apart baffles are positioned within the shell to force the stream to flow under and over them as it passes from the inlet to the outlet port. The baffles present a barrier to the microorganisms within the shell causing them to rise and fall within the reactor but to move horizontally at a very slow rate. Treatment detention times of one day or less are possible.

  1. Sustainable Energy: Choosing Among Options

    E-Print Network [OSTI]

    Mirza, Umar Karim

    2006-01-01T23:59:59.000Z

    Review: Sustainable Energy: Choosing Among Options Byand William A. Peters. Sustainable Energy: Choosing AmongAll the authors of Sustainable Energy are associated with

  2. Heterogeneous Recycling in Fast Reactors

    SciTech Connect (OSTI)

    Dr. Benoit Forget; Michael Pope; Piet, Steven J.; Michael Driscoll

    2012-07-30T23:59:59.000Z

    Current sodium fast reactor (SFR) designs have avoided the use of depleted uranium blankets over concerns of creating weapons grade plutonium. While reducing proliferation risks, this restrains the reactor design space considerably. This project will analyze various blanket and transmutation target configurations that could broaden the design space while still addressing the non-proliferation issues. The blanket designs will be assessed based on the transmutation efficiency of key minor actinide (MA) isotopes and also on mitigation of associated proliferation risks. This study will also evaluate SFR core performance under different scenarios in which depleted uranium blankets are modified to include minor actinides with or without moderators (e.g. BeO, MgO, B4C, and hydrides). This will be done in an effort to increase the sustainability of the reactor and increase its power density while still offering a proliferation resistant design with the capability of burning MA waste produced from light water reactors (LWRs). Researchers will also analyze the use of recycled (as opposed to depleted) uranium in the blankets. The various designs will compare MA transmutation efficiency, plutonium breeding characteristics, proliferation risk, shutdown margins and reactivity coefficients with a current reference sodium fast reactor design employing homogeneous recycling. The team will also evaluate the out-of-core accumulation and/or burn-down rates of MAs and plutonium isotopes on a cycle-by-cycle basis. This cycle-by-cycle information will be produced in a format readily usable by the fuel cycle systems analysis code, VISION, for assessment of the sustainability of the deployment scenarios.

  3. Corporate sustainability assessment methodology

    E-Print Network [OSTI]

    Pinchuk, Natallia

    2011-01-01T23:59:59.000Z

    Sustainability is a vague concept specifically in the context of a corporate world. There are numerous definitions for corporate sustainability and just as many ways of evaluating it. This work attempts to define, structure ...

  4. Sustainable Nanomaterials Workshop

    Broader source: Energy.gov [DOE]

    The Sustainable Nanomaterials Workshop (held in Washington, D.C., on June 26, 2012) gathered stakeholders from industry and academia to discuss the current state of the art for sustainable nanomat...

  5. Sustainability, Ethics, and Aesthetics

    E-Print Network [OSTI]

    Moldavanova, Alisa

    2013-01-01T23:59:59.000Z

    Among four dimensions of sustainability (environmental, economic, social, and cultural), it is the latter aspect that is least examined by scholars. However, understanding how culture contributes to the long term sustainability of communities...

  6. Biomarkers for Sustainable

    E-Print Network [OSTI]

    Predictive Biomarkers for Sustainable Environments For more information, contact: Ann Miracle for Sustainable Environments PaCIFIC NorThwEST NaTIoNaL LaBoraTory Detecting environmental damage before it's too

  7. Sustainable tourism in Russia.

    E-Print Network [OSTI]

    Khoroshavina, Sofya

    2010-01-01T23:59:59.000Z

    ??Im Jahr 1987 wurden im Brundtland Report erstmals das Konzept der Nachhaltigen Entwicklung („SustainableDevelopment“) sowie der Begriff Nachhaltiger Tourismus („SustainableTourism“) erwähnt. Seitdem wird diesen Prinzipien… (more)

  8. Sustainable Development Summer Intern Report 2010 Sustainable Development Summer Intern

    E-Print Network [OSTI]

    Sustainable Development Summer Intern Report 2010 1 Sustainable Development Summer Intern Final of Bishop's University. The role of the Sustainable Development Summer Intern (SDSI) is to coordinate and organize sustainable development information and activities during the summer months. Ensuring

  9. Sustainability Peer Educator Positions Position: Sustainability Peer Educator

    E-Print Network [OSTI]

    Boonstra, Rudy

    Sustainability Peer Educator Positions Position: Sustainability Peer Educator Available Positions 2013 ­ April 2014 Position Summary: Working with the Sustainability Project Coordinator, this team of students will be responsible for enhancing and educating UTSC students, staff and faculty on sustainability

  10. Sustainability Curriculum Models Sustainability Design Charrette Curriculum Workshop

    E-Print Network [OSTI]

    Zaferatos, Nicholas C.

    Sustainability Curriculum Models Sustainability Design Charrette Curriculum Workshop December 4 student that goes through WWU understands how sustainability is practiced on campus Students leave with a commitment, knowledge, and resources to practice sustainability in work and private life. Content

  11. Architecture, Engineering and Construction Sustainability Report Biannual Sustainability Report

    E-Print Network [OSTI]

    Kamat, Vineet R.

    Architecture, Engineering and Construction Sustainability Report i Biannual Sustainability Report Projects $5 Million and Over August 2012 Active Projects

  12. Neutronic reactor

    DOE Patents [OSTI]

    Wende, Charles W. J. (Augusta, GA); Babcock, Dale F. (Wilmington, DE); Menegus, Robert L. (Wilmington, DE)

    1983-01-01T23:59:59.000Z

    A nuclear reactor includes an active portion with fissionable fuel and neutron moderating material surrounded by neutron reflecting material. A control element in the active portion includes a group of movable rods constructed of neutron-absorbing material. Each rod is movable with respect to the other rods to vary the absorption of neutrons and effect control over neutron flux.

  13. STRATEGIC FOCUS: Sustainable Systems

    E-Print Network [OSTI]

    to apply sustain- ability principles to building and design, transportation and other fields, to green, presented an ecologically-sustainable sanitation system developed for a small hospital in northern Haiti1010 STRATEGIC FOCUS: Sustainable Systems Biology doctoral student Tanya Lubansky uses quan

  14. SUSTAINABILITY New Perspectives

    E-Print Network [OSTI]

    Edwards, Paul N.

    the basic principle of sustainability to all areas of human activity, from energy to all manner of consumerSUSTAINABILITY New Perspectives and Opportunities Globalization TrendLab 2012 #12;Globalization TrendLab 2012 Sustainability New Perspectives and Opportunities #12;Based on a conference organized

  15. UC Sustainability Office Report

    E-Print Network [OSTI]

    Hickman, Mark

    1 UC Sustainability Office Report Introduction Welcome to the second annual UC Sustainability Office Report. 2012 saw the Sustainability Office focus its attentions on enhancing the student experience and building on UC's statement of strategic intent of `people prepared to make a difference'. We

  16. Global Change Sustainability

    E-Print Network [OSTI]

    Tipple, Brett

    Global Change and Sustainability Center The GCSC is an inclusionary and interdisciplinary hub that promotes, coordinates, and conducts local to global environmental- and sustainability-related research to complex environmental and sustainability issues and challenges. 2012 Annual Report #12;1GCSC 2012 ANNUAL

  17. Sustainability and Horticulture

    E-Print Network [OSTI]

    Weiblen, George D

    N2O CH4 CO2 CO2 Sustainability and Horticulture: Examples from Tree Fruit Production David Granatstein WSU-Center for Sustaining Agriculture and Natural Resources Wenatchee, WA USA Kermit Olsen Lecture, St. Paul, MN, March 21, 2012 Yakima Valley #12;#12;CH4 Outline What is `sustainability' ? Global

  18. BERKSHIRE ENCYCLOPEDIA OF SUSTAINABILITY

    E-Print Network [OSTI]

    Kammen, Daniel M.

    BERKSHIRE ENCYCLOPEDIA OF SUSTAINABILITY V O L U M E S 1-10 A ground-breaking interdisciplinary@berkshirepublishing.com | Tel +1 413 528 0206 19 April, 2012 In the 10-volume Berkshire Encyclopedia of Sustainability, experts, regional sustainability issues, and resource and ecosystem management. The ten volumes are available

  19. SUSTAINABILITY WHO CAN APPLY

    E-Print Network [OSTI]

    FUNDED BY CALL FOR SUSTAINABILITY RESEARCH STUDENT WHO CAN APPLY Undergraduate and graduate Participate in the Global Change & Sustainability Center's Research Symposium; attend workshops with faculty or publish in the U's student-run sustainability publication to be released in May 2014. Are you conducting

  20. Sustainability Bulletin Clothing Collection

    E-Print Network [OSTI]

    Kidd, William S. F.

    Sustainability Bulletin April 2014 #12;Upcoming Clothing Collection March 3-April 14 Hunter Lovins on Wednesday, April 23rd from 11am-2pm brought to you by EAP and the Office of Environmental Sustainability will be in the Campus Center Ballroom to highlight other aspects of well-being such as health, nutrition, sustainability

  1. Sustainability Masters Programmes

    E-Print Network [OSTI]

    Sustainability Masters Programmes School of Earth and Environment FACULTY OF ENVIRONMENT #12 for sustainability (e.g. a low-carbon economy, or economic development that considers environmental and social issues) needs people with an in-depth understanding of sustainability and climate change issues. Forward

  2. Final Report Sustainability at

    E-Print Network [OSTI]

    Escher, Christine

    1 Final Report Sustainability at Oregon State University Prepared by The Institute for Natural Resources Oregon State University June 2009 #12;2 Sustainability at Oregon State University June 2009 The Institute for Natural Resources Created by the Oregon Legislature through the 2001 Oregon Sustainability Act

  3. Sustainability Initiative Executive Summary

    E-Print Network [OSTI]

    Sheridan, Jennifer

    UW­Madison Sustainability Initiative Executive Summary October 2010 #12;2 We are pleased to present the final report of the campus Sustainability Task Force. This report fulfills the charge we gave to sustainability for consideration by UW­Madison's leadership and campus community. There are many reasons why

  4. Social Sustainability: Geography 446

    E-Print Network [OSTI]

    Social Sustainability: Geography 446 submitted to Sally Hermansen & Lorna Seppala The University of British Columbia Vancouver, BC Curranne Labercane February 4th, 2009 #12;Definition Social Sustainability- A socially sustainable community provides an inclusive, equitable, and decent quality of life for current

  5. SUSTAINABLE DEVELOPMENT REPORT

    E-Print Network [OSTI]

    Laval, UniversitĂŠ

    ­ Encourage research and innovation in sustainable development 14 - Standard of Living, EconomySUSTAINABLE DEVELOPMENT REPORT 2011-2012 #12;2 Table of Contents UNIVERSIT� LAVAL AT A GLANCE 3 A WORD FROM THE RECTOR 4 A WORD FROM THE EXECUTIVE VICE-RECTOR, DEVELOPMENT 5 SUSTAINABLE DEVELOPMENT

  6. Lessons Learned From Gen I Carbon Dioxide Cooled Reactors

    SciTech Connect (OSTI)

    David E. Shropshire

    2004-04-01T23:59:59.000Z

    This paper provides a review of early gas cooled reactors including the Magnox reactors originating in the United Kingdom and the subsequent development of the Advanced Gas-cooled Reactors (AGR). These early gas cooled reactors shared a common coolant medium, namely carbon dioxide (CO2). A framework of information is provided about these early reactors and identifies unique problems/opportunities associated with use of CO2 as a coolant. Reactor designers successfully rose to these challenges. After years of successful use of the CO2 gas cooled reactors in Europe, the succeeding generation of reactors, called the High Temperature Gas Reactors (HTGR), were designed with Helium gas as the coolant. Again, in the 21st century, with the latest reactor designs under investigation in Generation IV, there is a revived interest in developing Gas Cooled Fast Reactors that use CO2 as the reactor coolant. This paper provides a historical perspective on the 52 CO2 reactors and the reactor programs that developed them. The Magnox and AGR design features and safety characteristics were reviewed, as well as the technologies associated with fuel storage, reprocessing, and disposal. Lessons-learned from these programs are noted to benefit the designs of future generations of gas cooled nuclear reactors.

  7. Unique features of space reactors

    SciTech Connect (OSTI)

    Buden, D.

    1990-01-01T23:59:59.000Z

    Space reactors are designed to meet a unique set of requirements; they must be sufficiently compact to be launched in a rocket to their operational location, operate for many years without maintenance and servicing, operate in extreme environments, and reject heat by radiation to space. To meet these restrictions, operating temperatures are much greater than in terrestrial power plants, and the reactors tend to have a fast neutron spectrum. Currently, a new generation of space reactor power plants is being developed. The major effort is in the SP-100 program, where the power plant is being designed for seven years of full power, and no maintenance operation at a reactor outlet operating temperature of 1350 K. 8 refs., 3 figs., 1 tab.

  8. Nuclear Reactors and Technology; (USA)

    SciTech Connect (OSTI)

    Cason, D.L.; Hicks, S.C. (eds.)

    1991-01-01T23:59:59.000Z

    Nuclear Reactors and Technology (NRT) announces on a monthly basis the current worldwide information available from the open literature on nuclear reactors and technology, including all aspects of power reactors, components and accessories, fuel elements, control systems, and materials. This publication contains the abstracts of DOE reports, journal articles, conference papers, patents, theses, and monographs added to the Energy Science and Technology Database (EDB) during the past month. Also included are US information obtained through acquisition programs or interagency agreements and international information obtained through the International Energy Agency's Energy Technology Data Exchange or government-to-government agreements. The digests in NRT and other citations to information on nuclear reactors back to 1948 are available for online searching and retrieval on EDB and Nuclear Science Abstracts (NSA) database. Current information, added daily to EDB, is available to DOE and its contractors through the DOE integrated Technical Information System. Customized profiles can be developed to provide current information to meet each user's needs.

  9. REACTOR ENGINEERING DIVISION QUARTERLY REPORT FOR DECEMBER 1...

    Office of Scientific and Technical Information (OSTI)

    reactor (physics, thermal analysis, and experimental and development program); corrosion of Al coating: irradiation of wax and lubricants; effect of long-term irradiation on...

  10. Reactor physics project progress report no. 2

    E-Print Network [OSTI]

    Driscoll, Michael J.

    1969-01-01T23:59:59.000Z

    This is the second annual report in an experimental and theoretical program to develop and apply single and few element heterogeneous methods for the determination of reactor lattice parameters. During the period covered ...

  11. E-Print Network 3.0 - allens creek-1 reactor Sample Search Results

    Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

    Centre de mathmatiques Collection: Mathematics 96 Proposed Program: Reliability-Centered Maintenance (RCM) for the High Flux Isotope Reactor Summary: Proposed Program:...

  12. E-Print Network 3.0 - argentine reactor ra-8 Sample Search Results

    Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

    Centre de mathmatiques Collection: Mathematics 88 Proposed Program: Reliability-Centered Maintenance (RCM) for the High Flux Isotope Reactor Summary: Proposed Program:...

  13. E-Print Network 3.0 - argentine reactor ra-3 Sample Search Results

    Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

    Centre de mathmatiques Collection: Mathematics 93 Proposed Program: Reliability-Centered Maintenance (RCM) for the High Flux Isotope Reactor Summary: Proposed Program:...

  14. E-Print Network 3.0 - acpr reactor Sample Search Results

    Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

    Centre de mathmatiques Collection: Mathematics 99 Proposed Program: Reliability-Centered Maintenance (RCM) for the High Flux Isotope Reactor Summary: Proposed Program:...

  15. E-Print Network 3.0 - annular reactor system Sample Search Results

    Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

    University Collection: Engineering ; Physics 95 Proposed Program: Reliability-Centered Maintenance (RCM) for the High Flux Isotope Reactor Summary: Proposed Program:...

  16. E-Print Network 3.0 - alto lazio-2 reactor Sample Search Results

    Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

    Centre de mathmatiques Collection: Mathematics 69 Proposed Program: Reliability-Centered Maintenance (RCM) for the High Flux Isotope Reactor Summary: Proposed Program:...

  17. E-Print Network 3.0 - argonaut lemont reactor Sample Search Results

    Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

    Centre de mathmatiques Collection: Mathematics 89 Proposed Program: Reliability-Centered Maintenance (RCM) for the High Flux Isotope Reactor Summary: Proposed Program:...

  18. E-Print Network 3.0 - autonomous reactor sstar Sample Search...

    Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

    Centre de mathmatiques Collection: Mathematics 87 Proposed Program: Reliability-Centered Maintenance (RCM) for the High Flux Isotope Reactor Summary: Proposed Program:...

  19. E-Print Network 3.0 - avogadro rs-1 reactor Sample Search Results

    Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

    Centre de mathmatiques Collection: Mathematics 88 Proposed Program: Reliability-Centered Maintenance (RCM) for the High Flux Isotope Reactor Summary: Proposed Program:...

  20. E-Print Network 3.0 - argus reactor Sample Search Results

    Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

    Centre de mathmatiques Collection: Mathematics 92 Proposed Program: Reliability-Centered Maintenance (RCM) for the High Flux Isotope Reactor Summary: Proposed Program:...

  1. E-Print Network 3.0 - astr reactor Sample Search Results

    Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

    Centre de mathmatiques Collection: Mathematics 91 Proposed Program: Reliability-Centered Maintenance (RCM) for the High Flux Isotope Reactor Summary: Proposed Program:...

  2. E-Print Network 3.0 - argentine reactor ra-4 Sample Search Results

    Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

    Centre de mathmatiques Collection: Mathematics 88 Proposed Program: Reliability-Centered Maintenance (RCM) for the High Flux Isotope Reactor Summary: Proposed Program:...

  3. E-Print Network 3.0 - alto lazio-1 reactor Sample Search Results

    Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

    Centre de mathmatiques Collection: Mathematics 68 Proposed Program: Reliability-Centered Maintenance (RCM) for the High Flux Isotope Reactor Summary: Proposed Program:...

  4. E-Print Network 3.0 - allens creek-2 reactor Sample Search Results

    Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

    Centre de mathmatiques Collection: Mathematics 92 Proposed Program: Reliability-Centered Maintenance (RCM) for the High Flux Isotope Reactor Summary: Proposed Program:...

  5. E-Print Network 3.0 - argonauta rio reactor Sample Search Results

    Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

    Centre de mathmatiques Collection: Mathematics 91 Proposed Program: Reliability-Centered Maintenance (RCM) for the High Flux Isotope Reactor Summary: Proposed Program:...

  6. E-Print Network 3.0 - apra reactor Sample Search Results

    Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

    Centre de mathmatiques Collection: Mathematics 86 Proposed Program: Reliability-Centered Maintenance (RCM) for the High Flux Isotope Reactor Summary: Proposed Program:...

  7. E-Print Network 3.0 - austrian triga-mark-ii reactor Sample Search...

    Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

    Centre de mathmatiques Collection: Mathematics 94 Proposed Program: Reliability-Centered Maintenance (RCM) for the High Flux Isotope Reactor Summary: Proposed Program:...

  8. E-Print Network 3.0 - astra reactor Sample Search Results

    Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

    Centre de mathmatiques Collection: Mathematics 100 Proposed Program: Reliability-Centered Maintenance (RCM) for the High Flux Isotope Reactor Summary: Proposed Program:...

  9. Better Buildings Residential Network Program Sustainability Peer Exchange Call Series: Coordinating Energy Efficiency with Water Conservation Services Call Slides and Discussion Summary September 11, 2014

    Office of Energy Efficiency and Renewable Energy (EERE) Indexed Site

    AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative Fuels Data Center Home Page on Google Bookmark EERE: Alternative Fuels Data Center Home Page on Delicious Rank EERE:YearRound-Up fromDepartmentTie Ltd: ScopeDepartment1, 2011 BetterOctober25, 2013 Program

  10. Sustainable Supply Chain Networks Sustainable Cities

    E-Print Network [OSTI]

    Nagurney, Anna

    years since the industrial revolution (Burruss (2004)). Anna Nagurney Sustainability #12;Pollution, and natural gas), has risen 30% in the 200 years since the industrial revolution (Burruss (2004)). The average

  11. Design of Sustainable Supply Chains Sustainable Cities

    E-Print Network [OSTI]

    Nagurney, Anna

    years since the industrial revolution (Burruss (2004)). Anna Nagurney Sustainability #12;Pollution, and natural gas), has risen 30% in the 200 years since the industrial revolution (Burruss (2004)). The average

  12. CRC handbook of nuclear reactors calculations. Vol. III

    SciTech Connect (OSTI)

    Ronen, Y.

    1986-01-01T23:59:59.000Z

    This handbook breaks down the complex field of nuclear reactor calculations into major steps. Each step presents a detailed analysis of the problems to be solved, the parameters involved, and the elaborate computer programs developed to perform the calculations. This book bridges the gap between nuclear reactor theory and the implementation of that theory, including the problems to be encountered and the level of confidence that should be given to the methods described. Volume III: Control Rods and Burnable Absorber Calculations. Perturbation Theory for Nuclear Reactor Analysis. Thermal Reactors Calculations. Fast Reactor Calculations. Seed-Blanket Reactors. Index.

  13. Sustainable Urban Development: A Literature Review and Analysis

    E-Print Network [OSTI]

    Wheeler, Stephen

    1996-01-01T23:59:59.000Z

    Towards Sustainable Development and Sustainable Urban Forms,Sustainable Urban Development Sustainable Seattle Indicatorseds. , Making Development Sustainable: From Concepts to

  14. Updating reactor control: mini-computers

    SciTech Connect (OSTI)

    Crawford, K.C.; Sandquist, G.M. [University of Utah, Salt Lake City, UT (United States)

    1984-07-01T23:59:59.000Z

    An aging reactor control console and a limited operating budget have impeded many research projects in the TRIGA reactor facility at the University of Utah. The, University's present console is Circa 1959 vintage and repairs to the console are frequently required which present many electronic problems to a staff with little electronic training. As an alternative to a single function control console we are developing a TRIGA control system based upon a mini-computer. The system hardware has been specified and the hardware is currently being acquired. The software will be programmed by the staff to customize the system to the reactor's physical systems and technical specifications. The software will be designed to monitor and control all reactor functions, control a pneumatic sample transfer system, acquire and analyze neutron activation data, provide reactor facility security surveillance, provide reactor documentation including online logging of physical parameters, and record regularly scheduled reactor calibrations and laboratory accounting procedures. The problem of hardware rewiring and changing technical specifications and changing safety system characteristics can be easily handled in the software. Our TRIGA reactor also functions as a major educational resource using available reactor based software. The computer control system can be employed to provide on-line training in reactor physics and kinetics. (author)

  15. Canada Research Chair, Tier II in Economics of Sustainable Development

    E-Print Network [OSTI]

    Martin, Jeff

    Canada Research Chair, Tier II in Economics of Sustainable Development The University of Winnipeg has designated a Tier II Canada Research Chair in the Economics of Sustainable Development within and enhanced research support. The Canada Research Chair program was established by the Government of Canada

  16. Sustainable Building Basics

    Broader source: Energy.gov [DOE]

    Sustainable building design and operation strategies demonstrate a commitment to energy efficiency, and environmental stewardship. These approaches result in an optimal balance of energy, cost, environmental, and societal benefits, while still meeting the mission of a Federal agency and the function of the facility or infrastructure. For buildings and facilities, responsible resource management and the assessment of operational impacts encompass the principles of sustainability. Sustainable development aims to meet the needs of the present without compromising future needs.

  17. Implementation of Sustainability at

    E-Print Network [OSTI]

    Johansen, Tom Henning

    0 Assessing Implementation of Sustainability at UiO Grønt UiO S u s t a i n a b i l i t y i n R e sustainability commitment among universities and proposed Best Green University Practices in 2010. It presents the current status of UiO Environmental Sustainability. #12;1 If you cannot measure it, you cannot manage it

  18. JSC Sustainability Engagement Strategy

    E-Print Network [OSTI]

    Peterson, L.

    2012-01-01T23:59:59.000Z

    ? Joel Walker, our Center Sustainability Officer, says ?Sustainability should be something we don?t even think about; it should be engrained in our thinking. We just do it.? ? Mike Coats, JSC Center Director, and Joel Walker empower you to begin... Technical Solutions ? JSC Sustainability Partnership Team (SPT) ? Contact Mike Ewert (EC) to join! ? Ensure Contractor Involvement ? Contractor Environmental Partnership ? Contact Jennifer Morrison (JA/ERT) to join! 13 14 People: (Ms. Laurie...

  19. Design of Sustainable Supply Chains for Sustainable Cities Anna Nagurney

    E-Print Network [OSTI]

    Nagurney, Anna

    Design of Sustainable Supply Chains for Sustainable Cities Anna Nagurney Isenberg School of sustainable supply chains with a focus on cities that captures the frequency of network link operations, which and frequency costs, and meeting demand. Keywords: sustainable cities, supply chains, sustainability, network

  20. Financing Sustainable EnergyFinancing Sustainable Energy City of Berkeley

    E-Print Network [OSTI]

    Kammen, Daniel M.

    Financing Sustainable EnergyFinancing Sustainable Energy City of Berkeley #12;Source of Green House for Sustainable EnergyFramework for Sustainable Energy Financing District ˇ Adopted new Special Tax Financing Law indebtedness by unanimous consent of property owner #12;Framework for Sustainable Energy