Sample records for nuclear propulsion program

  1. Importance of Nuclear DataImportance of Nuclear Data to the Naval Nuclear Propulsion Program

    E-Print Network [OSTI]

    Danon, Yaron

    Importance of Nuclear DataImportance of Nuclear Data to the Naval Nuclear Propulsion Program Don Cores · Project Prometheus · Some Very Recent Criticality Analyses #12;Use of Early RPI Measurements · Criticality Analyses of Under-moderated Systemsy y y · Most Reactive Condition ­ Highest Water Density

  2. Nuclear Propulsion in Space (1968)

    SciTech Connect (OSTI)

    None

    2012-06-23T23:59:59.000Z

    Project NERVA was an acronym for Nuclear Engine for Rocket Vehicle Application, a joint program of the U.S. Atomic Energy Commission and NASA managed by the Space Nuclear Propulsion Office (SNPO) at the Nuclear Rocket Development Station in Jackass Flats, Nevada U.S.A. Between 1959 and 1972, the Space Nuclear Propulsion Office oversaw 23 reactor tests, both the program and the office ended at the end of 1972.

  3. Nuclear Propulsion in Space (1968)

    ScienceCinema (OSTI)

    None

    2014-06-17T23:59:59.000Z

    Project NERVA was an acronym for Nuclear Engine for Rocket Vehicle Application, a joint program of the U.S. Atomic Energy Commission and NASA managed by the Space Nuclear Propulsion Office (SNPO) at the Nuclear Rocket Development Station in Jackass Flats, Nevada U.S.A. Between 1959 and 1972, the Space Nuclear Propulsion Office oversaw 23 reactor tests, both the program and the office ended at the end of 1972.

  4. An overview of the Nuclear Electric Propulsion Space Test Program (NEPSTP) satellite

    SciTech Connect (OSTI)

    Voss, S.S. [Los Alamos National Lab., NM (United States); Reynolds, E.L. [Applied Physics Laboratory, Laurel, MD (United States)

    1994-06-01T23:59:59.000Z

    Early in 1992 the idea of purchasing a Russian designed and fabricated space reactor power system and integrating it with a US designed satellite went from fiction to reality with the purchase of the first two Topaz II reactors by the Strategic Defense Initiative Organization (now the Ballistic Missile Defense Organization (BMDO). The New Mexico Alliance was formed to establish a ground test facility in which to perform nonnuclear systems testing of the Topaz II, and to evaluate the Topaz 11 system for flight testing with respect to safety, performance, and operability. In conjunction, SDIO requested that the Applied Physics Laboratory in Laurel, MD propose a mission and design a satellite in which the Topaz II could be used as the power source. The outcome of these two activities was the design of the Nuclear Electric Propulsion Space Test Program (NEPSTP) satellite which combines a modified Russian Topaz II power system with a US designed satellite to achieve a specified mission. Due to funding reduction within the SDIO, the Topaz II flight program was postponed indefinitely at the end of Fiscal Year 1993. The purpose of this paper is to present an overview of the NEPSTP mission and the satellite design at the time the flight program ended.

  5. Pure Nuclear Fusion Bomb Propulsion

    E-Print Network [OSTI]

    Winterberg, F

    2008-01-01T23:59:59.000Z

    Recent progress towards the non-fission ignition of thermonuclear micro-explosions raises the prospect for a revival of the nuclear bomb propulsion idea, both for the fast transport of large payloads within the solar system and the launch into earth orbit without the release of fission products into the atmosphere. To reach this goal three areas of research are of importance: 1)Compact thermonuclear ignition drivers. 2)Fast ignition and deuterium burn. 3)Space-craft architecture involving magnetic insulation and GeV electrostatic potentials

  6. Ultrahigh Specific Impulse Nuclear Thermal Propulsion

    SciTech Connect (OSTI)

    Anne Charmeau; Brandon Cunningham; Samim Anghaie

    2009-02-09T23:59:59.000Z

    Research on nuclear thermal propulsion systems (NTP) have been in forefront of the space nuclear power and propulsion due to their design simplicity and their promise for providing very high thrust at reasonably high specific impulse. During NERVA-ROVER program in late 1950's till early 1970's, the United States developed and ground tested about 18 NTP systems without ever deploying them into space. The NERVA-ROVER program included development and testing of NTP systems with very high thrust (~250,000 lbf) and relatively high specific impulse (~850 s). High thrust to weight ratio in NTP systems is an indicator of high acceleration that could be achieved with these systems. The specific impulse in the lowest mass propellant, hydrogen, is a function of square root of absolute temperature in the NTP thrust chamber. Therefor optimizing design performance of NTP systems would require achieving the highest possible hydrogen temperature at reasonably high thrust to weight ratio. High hydrogen exit temperature produces high specific impulse that is a diret measure of propellant usage efficiency.

  7. Nuclear propulsion system options for Mars missions

    SciTech Connect (OSTI)

    Emrich, W.J. Jr.; Young, A.C. (NASA, Marshall Space Flight Center, Huntsville, AL (United States))

    1992-03-01T23:59:59.000Z

    This paper focuses on the use of a nuclear thermal rocket to accomplish a variety of space missions with emphasis on the manned Mars mission. The particle-bed-reactor type nuclear engine was chosen as the baseline engine because of its perceived versatility over other nuclear propulsion systems in conducting a wide variety of tasks. This study indicates that the particle-bed-reactor engine with its high engine thrust-to-weight ratio (about 20) and high specific impulse (about 950 to 1050 sec) offers distinct advantages over the larger and heavier NERVA-type nuclear engines.

  8. Current Development of Nuclear Thermal Propulsion technologies at the Center for Space Nuclear Research

    SciTech Connect (OSTI)

    Robert C. O'Brien; Steven K. Cook; Nathan D. Jerred; Steven D. Howe; Ronald Samborsky; Daniel Brasuell

    2012-09-01T23:59:59.000Z

    Nuclear power and propulsion has been considered for space applications since the 1950s. Between 1955 and 1972 the US built and tested over twenty nuclear reactors / rocket engines in the Rover/NERVA programs1. The Aerojet Corporation was the prime contractor for the NERVA program. Modern changes in environmental laws present challenges for the redevelopment of the nuclear rocket. Recent advances in fuel fabrication and testing options indicate that a nuclear rocket with a fuel composition that is significantly different from those of the NERVA project can be engineered; this may be needed to ensure public support and compliance with safety requirements. The Center for Space Nuclear Research (CSNR) is pursuing a number of technologies, modeling and testing processes to further the development of safe, practical and affordable nuclear thermal propulsion systems.

  9. aircraft nuclear propulsion: Topics by E-print Network

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

    engine technologies mature. Significant (more) Kirner, Rudi 2013-01-01 3 Pure Nuclear Fusion Bomb Propulsion CERN Preprints Summary: Recent progress towards the non-fission...

  10. Nuclear rockets: High-performance propulsion for Mars

    SciTech Connect (OSTI)

    Watson, C.W.

    1994-05-01T23:59:59.000Z

    A new impetus to manned Mars exploration was introduced by President Bush in his Space Exploration Initiative. This has led, in turn, to a renewed interest in high-thrust nuclear thermal rocket propulsion (NTP). The purpose of this report is to give a brief tutorial introduction to NTP and provide a basic understanding of some of the technical issues in the realization of an operational NTP engine. Fundamental physical principles are outlined from which a variety of qualitative advantages of NTP over chemical propulsion systems derive, and quantitative performance comparisons are presented for illustrative Mars missions. Key technologies are described for a representative solid-core heat-exchanger class of engine, based on the extensive development work in the Rover and NERVA nuclear rocket programs (1955 to 1973). The most driving technology, fuel development, is discussed in some detail for these systems. Essential highlights are presented for the 19 full-scale reactor and engine tests performed in these programs. On the basis of these tests, the practicality of graphite-based nuclear rocket engines was established. Finally, several higher-performance advanced concepts are discussed. These have received considerable attention, but have not, as yet, developed enough credibility to receive large-scale development.

  11. NSPWG-recommended safety requirements and guidelines for SEI nuclear propulsion

    SciTech Connect (OSTI)

    Marshall, A.C.; Sawyer, J.C. Jr.; Bari, R.A.; Brown, N.W.; Cullingford, H.S.; Hardy, A.C.; Lee, J.H.; Mcculloch, W.H.; Niederauer, G.F.; Remp, K. (Sandia National Laboratories, Albuquerque, NM (United States) NASA, Washington (United States) Brookhaven National Laboratory, Upton, NY (United States) General Electric Co., San Jose, CA (United States) NASA, Johnson Space Center, Houston, Tn (United States) L

    1992-07-01T23:59:59.000Z

    An interagency Nuclear Safety Policy Working Group (NSPWG) was chartered to recommend nuclear safety policy, requirements, and guidelines for the Space Exploration Initiative (SEI) nuclear propulsion program to facilitate the implementation of mission planning and conceptual design studies. The NSPWG developed a top-level policy to provide the guiding principles for the development and implementation of the nuclear propulsion safety program and the development of safety functional requirements. In addition, the NSPWG reviewed safety issues for nuclear propulsion and recommended top-level safety requirements and guidelines to address these issues. Safety requirements were developed for reactor start-up, inadvertent criticality, radiological release and exposure, disposal, entry, and safeguards. Guidelines were recommended for risk/reliability, operational safety, flight trajectory and mission abort, space debris and meteoroids, and ground test safety. In this paper the specific requirements and guidelines will be discussed. 9 refs.

  12. NSPWG-recommended safety requirements and guidelines for SEI nuclear propulsion

    SciTech Connect (OSTI)

    Marshall, A.C.; Lee, J.H.; McCulloch, W.H. (Sandia National Labs., Albuquerque, NM (United States)); Sawyer, J.C. Jr. (National Aeronautics and Space Administration, Washington, DC (United States)); Bari, R.A. (Brookhaven National Lab., Upton, NY (United States)); Brown, N.W. (General Electric Co., San Jose, CA (United States)); Cullingford, H.S.; Hardy, A.C. (National Aeronautics and Space Administ

    1992-01-01T23:59:59.000Z

    An Interagency Nuclear Safety Policy Working Group (NSPWG) was chartered to recommend nuclear safety policy, requirements, and guidelines for the Space Exploration Initiative (SEI) nuclear propulsion program to facilitate the implementation of mission planning and conceptual design studies. The NSPWG developed a top- level policy to provide the guiding principles for the development and implementation of the nuclear propulsion safety program and the development of Safety Functional Requirements. In addition the NSPWG reviewed safety issues for nuclear propulsion and recommended top-level safety requirements and guidelines to address these issues. Safety requirements were developed for reactor start-up, inadvertent criticality, radiological release and exposure, disposal, entry, and safeguards. Guidelines were recommended for risk/reliability, operational safety, flight trajectory and mission abort, space debris and meteoroids, and ground test safety. In this paper the specific requirements and guidelines will be discussed.

  13. NSPWG-recommended safety requirements and guidelines for SEI nuclear propulsion

    SciTech Connect (OSTI)

    Marshall, A.C.; Lee, J.H.; McCulloch, W.H. [Sandia National Labs., Albuquerque, NM (United States); Sawyer, J.C. Jr. [National Aeronautics and Space Administration, Washington, DC (United States); Bari, R.A. [Brookhaven National Lab., Upton, NY (United States); Brown, N.W. [General Electric Co., San Jose, CA (United States); Cullingford, H.S.; Hardy, A.C. [National Aeronautics and Space Administration, Houston, TX (United States). Lyndon B. Johnson Space Center; Niederauer, G.F. [Los Alamos National Lab., NM (United States); Remp, K. [National Aeronautics and Space Administration, Cleveland, OH (United States). Lewis Research Center; Rice, J.W. [Idaho National Engineering Lab., Idaho Falls, ID (United States); Sholtis, J.A. [Department of the Air Force, Kirtland AFB, NM (United States)

    1992-09-01T23:59:59.000Z

    An Interagency Nuclear Safety Policy Working Group (NSPWG) was chartered to recommend nuclear safety policy, requirements, and guidelines for the Space Exploration Initiative (SEI) nuclear propulsion program to facilitate the implementation of mission planning and conceptual design studies. The NSPWG developed a top- level policy to provide the guiding principles for the development and implementation of the nuclear propulsion safety program and the development of Safety Functional Requirements. In addition the NSPWG reviewed safety issues for nuclear propulsion and recommended top-level safety requirements and guidelines to address these issues. Safety requirements were developed for reactor start-up, inadvertent criticality, radiological release and exposure, disposal, entry, and safeguards. Guidelines were recommended for risk/reliability, operational safety, flight trajectory and mission abort, space debris and meteoroids, and ground test safety. In this paper the specific requirements and guidelines will be discussed.

  14. Small Reactor Designs Suitable for Direct Nuclear Thermal Propulsion: Interim Report

    SciTech Connect (OSTI)

    Bruce G. Schnitzler

    2012-01-01T23:59:59.000Z

    Advancement of U.S. scientific, security, and economic interests requires high performance propulsion systems to support missions beyond low Earth orbit. A robust space exploration program will include robotic outer planet and crewed missions to a variety of destinations including the moon, near Earth objects, and eventually Mars. Past studies, in particular those in support of both the Strategic Defense Initiative (SDI) and the Space Exploration Initiative (SEI), have shown nuclear thermal propulsion systems provide superior performance for high mass high propulsive delta-V missions. In NASA's recent Mars Design Reference Architecture (DRA) 5.0 study, nuclear thermal propulsion (NTP) was again selected over chemical propulsion as the preferred in-space transportation system option for the human exploration of Mars because of its high thrust and high specific impulse ({approx}900 s) capability, increased tolerance to payload mass growth and architecture changes, and lower total initial mass in low Earth orbit. The recently announced national space policy2 supports the development and use of space nuclear power systems where such systems safely enable or significantly enhance space exploration or operational capabilities. An extensive nuclear thermal rocket technology development effort was conducted under the Rover/NERVA, GE-710 and ANL nuclear rocket programs (1955-1973). Both graphite and refractory metal alloy fuel types were pursued. The primary and significantly larger Rover/NERVA program focused on graphite type fuels. Research, development, and testing of high temperature graphite fuels was conducted. Reactors and engines employing these fuels were designed, built, and ground tested. The GE-710 and ANL programs focused on an alternative ceramic-metallic 'cermet' fuel type consisting of UO2 (or UN) fuel embedded in a refractory metal matrix such as tungsten. The General Electric program examined closed loop concepts for space or terrestrial applications as well as open loop systems for direct nuclear thermal propulsion. Although a number of fast spectrum reactor and engine designs suitable for direct nuclear thermal propulsion were proposed and designed, none were built. This report summarizes status results of evaluations of small nuclear reactor designs suitable for direct nuclear thermal propulsion.

  15. NASA/DOE/DOD nuclear propulsion technology planning: Summary of FY 1991 interagency panel results

    SciTech Connect (OSTI)

    Clark, J.S.; Wickenheiser, T.J.; Doherty, M.P.; Marshall, A.; Bhattacharryya, S.K.; Warren, J.

    1992-01-01T23:59:59.000Z

    Interagency (NASA/DOE/DOD) technical panels worked in 1991 to evaluate critical nuclear propulsion issues, compare nuclear propulsion concepts for a manned Mars mission on a consistent basis, and to continue planning a technology development project for the Space Exploration Initiative (SEI). Panels were formed to address mission analysis, nuclear facilities, safety policy, nuclear fuels and materials, nuclear electric propulsion technology, and nuclear thermal propulsion technology. A summary of the results and recommendations of the panels is presented.

  16. Tutorial on nuclear thermal propulsion safety for Mars

    SciTech Connect (OSTI)

    Buden, D.

    1992-01-01T23:59:59.000Z

    Safety is the prime design requirement for nuclear thermal propulsion (NTP). It must be built in at the initiation of the design process. An understanding of safety concerns is fundamental to the development of nuclear rockets for manned missions to Mars and many other applications that will be enabled or greatly enhanced by the use of nuclear propulsion. To provide an understanding of the basic issues, a tutorial has been prepared. This tutorial covers a range of topics including safety requirements and approaches to meet these requirements, risk and safety analysis methodology, NERVA reliability and safety approach, and life cycle risk assessments.

  17. Tutorial on nuclear thermal propulsion safety for Mars

    SciTech Connect (OSTI)

    Buden, D.

    1992-08-01T23:59:59.000Z

    Safety is the prime design requirement for nuclear thermal propulsion (NTP). It must be built in at the initiation of the design process. An understanding of safety concerns is fundamental to the development of nuclear rockets for manned missions to Mars and many other applications that will be enabled or greatly enhanced by the use of nuclear propulsion. To provide an understanding of the basic issues, a tutorial has been prepared. This tutorial covers a range of topics including safety requirements and approaches to meet these requirements, risk and safety analysis methodology, NERVA reliability and safety approach, and life cycle risk assessments.

  18. Space nuclear power, propulsion, and related technologies.

    SciTech Connect (OSTI)

    Berman, Marshall

    1992-01-01T23:59:59.000Z

    Sandia National Laboratories (Sandia) is one of the nation's largest research and development (R&D) facilities, with headquarters at Albuquerque, New Mexico; a laboratory at Livermore, California; and a test range near Tonopah, Nevada. Smaller testing facilities are also operated at other locations. Established in 1945, Sandia was operated by the University of California until 1949, when, at the request of President Truman, Sandia Corporation was formed as a subsidiary of Bell Lab's Western Electric Company to operate Sandia as a service to the U.S. Government without profit or fee. Sandia is currently operated for the U.S. Department of Energy (DOE) by AT&T Technologies, Inc., a wholly-owned subsidiary of AT&T. Sandia's responsibility is national security programs in defense and energy with primary emphasis on nuclear weapon research and development (R&D). However, Sandia also supports a wide variety of projects ranging from basic materials research to the design of specialized parachutes. Assets, owned by DOE and valued at more than $1.2 billion, include about 600 major buildings containing about 372,000 square meters (m2) (4 million square feet [ft2]) of floor space, located on land totalling approximately 1460 square kilometers (km2) (562 square miles [mi]). Sandia employs about 8500 people, the majority in Albuquerque, with about 1000 in Livermore. Approximately 60% of Sandia's employees are in technical and scientific positions, and the remainder are in crafts, skilled labor, and administrative positions. As a multiprogram national laboratory, Sandia has much to offer both industrial and government customers in pursuing space nuclear technologies. The purpose of this brochure is to provide the reader with a brief summary of Sandia's technical capabilities, test facilities, and example programs that relate to military and civilian objectives in space. Sandia is interested in forming partnerships with industry and government organizations, and has already formed several cooperative alliances and agreements. Because of the synergism of multiple governmental and industrial sponsors of many programs, Sandia is frequently able to provide complex technical solutions in a relatively short time, and often at lower cost to a particular customer. They have listed a few ongoing programs at Sandia related to space nuclear technology as examples of the possible synergisms that could result from forming teams and partnerships with related technologies and objectives.

  19. REIMR - A Process for Utilizing Liquid Rocket Propulsion-Oriented 'Lessons Learned' to Mitigate Development Risk in Nuclear Thermal Propulsion

    SciTech Connect (OSTI)

    Ballard, Richard O. [Nuclear and Advanced Propulsion Systems Engineering Branch, NASA Marshall Space Flight Center, AL 35812 (United States)

    2006-01-20T23:59:59.000Z

    This paper is a summary overview of a study conducted at the NASA Marshall Space Flight Center (NASA-MSFC) during the initial phases of the Space Launch Initiative (SLI) program to evaluate a large number of technical problems associated with the design, development, test, evaluation and operation of several major liquid propellant rocket engine systems (i.e., SSME, Fastrac, J-2, F-1). One of the primary results of this study was the identification of the 'Fundamental Root Causes' that enabled the technical problems to manifest, and practices that can be implemented to prevent them from recurring in future propulsion system development efforts, such as that which is currently envisioned in the field of nuclear thermal propulsion (NTP). This paper will discus the Fundamental Root Causes, cite some examples of how the technical problems arose from them, and provide a discussion of how they can be mitigated or avoided in the development of an NTP system.

  20. Scoping calculations of power sources for nuclear electric propulsion

    SciTech Connect (OSTI)

    Difilippo, F.C. [Oak Ridge National Lab., TN (United States)] [Oak Ridge National Lab., TN (United States)

    1994-05-01T23:59:59.000Z

    This technical memorandum describes models and calculational procedures to fully characterize the nuclear island of power sources for nuclear electric propulsion. Two computer codes were written: one for the gas-cooled NERVA derivative reactor and the other for liquid metal-cooled fuel pin reactors. These codes are going to be interfaced by NASA with the balance of plant in order to making scoping calculations for mission analysis.

  1. Vehicle configuration options using nuclear propulsion for Mars missions

    SciTech Connect (OSTI)

    Emrich, W.J. Jr. (NASA-Marshall Space Flight Center, Huntsville, Alabama 35812 (United States))

    1993-01-20T23:59:59.000Z

    The solid core nuclear thermal rocket (NTR) provides an attractive means of providing the propulsive force needed to accomplish a wide array of space missions. With its factor of two or more advantage in Isp over chemical engines, nuclear propulsion provides the opportunity to accomplish space missions which are impractical by other means. This paper focuses on the use of a nuclear thermal rocket to accomplish a variety of space missions with emphasis on the manned Mars mission. The particle bed reactor (PBR) type nuclear engine was chosen as the baseline engine used to conduct the present study because of its perceived versatility over other nuclear propulsion systems in conducting a wide variety of tasks. This study baselines a particle bed reactor engine with an engine thrust-to-weight ratio ([similar to]11.5) and a specific impulse of [similar to]950 s. It is shown that a PBR engine of this type will offer distinct advantages over the larger and heavier NERVA type nuclear engines.

  2. Assessment of Space Nuclear Thermal Propulsion Facility and Capability Needs

    SciTech Connect (OSTI)

    James Werner

    2014-07-01T23:59:59.000Z

    The development of a Nuclear Thermal Propulsion (NTP) system rests heavily upon being able to fabricate and demonstrate the performance of a high temperature nuclear fuel as well as demonstrating an integrated system prior to launch. A number of studies have been performed in the past which identified the facilities needed and the capabilities available to meet the needs and requirements identified at that time. Since that time, many facilities and capabilities within the Department of Energy have been removed or decommissioned. This paper provides a brief overview of the anticipated facility needs and identifies some promising concepts to be considered which could support the development of a nuclear thermal propulsion system. Detailed trade studies will need to be performed to support the decision making process.

  3. Heavy Vehicle Propulsion Materials Program: Progress and Highlights

    SciTech Connect (OSTI)

    D. Ray Johnson; Sidney Diamond

    2000-06-19T23:59:59.000Z

    The Heavy Vehicle Propulsion Materials Program was begun in 1997 to support the enabling materials needs of the DOE Office of Heavy Vehicle Technologies (OHVT). The technical agenda for the program grew out of the technology roadmap for the OHVT and includes efforts in materials for: fuel systems, exhaust aftertreatment, valve train, air handling, structural components, electrochemical propulsion, natural gas storage, and thermal management. A five-year program plan was written in early 2000, following a stakeholders workshop. The technical issues and planned and ongoing projects are discussed. Brief summaries of several technical highlights are given.

  4. Nuclear Nonproliferation Programs | ORNL

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

    Nuclear Nonproliferation Programs SHARE Nuclear Nonproliferation Programs image Oak Ridge National Laboratory covers the entire spectrum of nuclear nonproliferation work, from...

  5. Nuclear space power and propulsion requirements and issues

    SciTech Connect (OSTI)

    Swerdling, M. [IR Associates, North Hills, CA (United States); Isenberg, L. [IR Associates, La Habra, CA (United States)

    1995-12-31T23:59:59.000Z

    The use of nuclear power in space is going through a low point. The kinds of missions that would use nuclear power are expensive and there are few new expensive missions. Both NASA and DoD are in a mode of cheaper, faster, better, which means using what is available as much as possible and only incorporating new technology to reduce mission cost. NASA is performing Mission to Planet Earth and detailed exploration missions of Mars. These NASA missions can be done with solar-battery power subsystems and there is no need for nuclear power. The NASA mission to Pluto does require nuclear radioisotope power. Ways to reduce the power subsystem cost and the power level are being investigated. NASA is studying ways to explore beyond Mars with solar-battery power because of the cost and uncertainty in the availability and launchability of nuclear space power systems. The DoD missions are all in earth orbit and can be done with solar-battery systems. The major DoD requirement at present is to reduce costs of all their space missions. One way to do this is to develop highly efficient upper stage boosters that can be integrated with lower cost Earth to low orbit stages and still place their payloads in to higher orbits. One attractive upper stage is a nuclear bimodal (propulsion and power) engine to accomplished lower booster cost to place space assets in GEO. However this is not being pursued because of DOE`s new policy not to fund nuclear space power research and development as well as the difficulty in obtaining launch approval for nuclear propulsion and power systems.

  6. Definition, Expansion and Screening of Architectures for Planetary Exploration Class Nuclear Electric Propulsion and Power Systems

    E-Print Network [OSTI]

    Nuclear Electric Propulsion and Power Systems By Bryan K. Smith Submitted to the System Design, expansion and screening of Nuclear Electric Propulsion and Power concepts capable of achieving planetaryDefinition, Expansion and Screening of Architectures for Planetary Exploration Class Nuclear

  7. Naval Nuclear Propulsion Plants | National Nuclear Security Administration

    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 May JunDatastreamsmmcrcalgovInstrumentsrucLas Conchas recoveryLaboratory | NationalJohn Cyber Security NuclearNewNatural

  8. Naval Nuclear Propulsion Plants | National Nuclear Security Administration

    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 May JunDatastreamsmmcrcalgovInstrumentsrucLas Conchas recoveryLaboratory | NationalJohn Cyber Security NuclearNewNaturalOur Mission /

  9. Technology survey and performance scaling for the design of high power nuclear electric power and propulsion systems

    E-Print Network [OSTI]

    White, Daniel B., Jr

    2011-01-01T23:59:59.000Z

    High power nuclear electric propulsion systems have the capability to enable many next-generation space exploration applications. To date, use of electric primary propulsion in flight systems has been limited to low-power, ...

  10. Categorical Exclusion Determinations: Naval Nuclear Propulsion Program |

    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:JuneNovember 26,Energy Service Center

  11. A New Capability for Nuclear Thermal Propulsion Design

    SciTech Connect (OSTI)

    Amiri, Benjamin W. [Nuclear Systems Design Group, Los Alamos National Laboratory, Los Alamos, NM 87545 (United States); Nuclear and Radiological Engineering Department, University of Florida, Gainesville, FL 32611 (United States); Kapernick, Richard J. [Nuclear Systems Design Group, Los Alamos National Laboratory, Los Alamos, NM 87545 (United States); Sims, Bryan T. [Nuclear Systems Design Group, Los Alamos National Laboratory, Los Alamos, NM 87545 (United States); School of Nuclear Engineering, Purdue University, West Lafayette, IN 47907 (United States); Simpson, Steven P. [NASA Marshall Space Flight Center, Huntsville, AL 35812 (United States)

    2007-01-30T23:59:59.000Z

    This paper describes a new capability for Nuclear Thermal Propulsion (NTP) design that has been developed, and presents the results of some analyses performed with this design tool. The purpose of the tool is to design to specified mission and material limits, while maximizing system thrust to weight. The head end of the design tool utilizes the ROCket Engine Transient Simulation (ROCETS) code to generate a system design and system design requirements as inputs to the core analysis. ROCETS is a modular system level code which has been used extensively in the liquid rocket engine industry for many years. The core design tool performs high-fidelity reactor core nuclear and thermal-hydraulic design analysis. At the heart of this process are two codes TMSS-NTP and NTPgen, which together greatly automate the analysis, providing the capability to rapidly produce designs that meet all specified requirements while minimizing mass. A PERL based command script, called CORE DESIGNER controls the execution of these two codes, and checks for convergence throughout the process. TMSS-NTP is executed first, to produce a suite of core designs that meet the specified reactor core mechanical, thermal-hydraulic and structural requirements. The suite of designs consists of a set of core layouts and, for each core layout specific designs that span a range of core fuel volumes. NTPgen generates MCNPX models for each of the core designs from TMSS-NTP. Iterative analyses are performed in NTPgen until a reactor design (fuel volume) is identified for each core layout that meets cold and hot operation reactivity requirements and that is zoned to meet a radial core power distribution requirement.

  12. Innovative nuclear thermal propulsion technology evaluation: Results of the NASA/DOE Task Team study

    SciTech Connect (OSTI)

    Howe, S. (Los Alamos National Lab., NM (United States)); Borowski, S. (National Aeronautics and Space Administration, Cleveland, OH (United States). Lewis Research Center); Motloch, C. (EG and G Idaho, Inc., Idaho Falls, ID (United States)); Helms, I. (Nuclear Utility Services, Damascus, MD (United States)); Diaz, N.; Anghaie, S. (Florida Univ., Gainesville, FL (United States)); Latham, T. (United

    1991-01-01T23:59:59.000Z

    In response to findings from two NASA/DOE nuclear propulsion workshops held in the summer of 1990, six task teams were formed to continue evaluation of various nuclear propulsion concepts. The Task Team on Nuclear Thermal Propulsion (NTP) created the Innovative Concepts Subpanel to evaluate thermal propulsion concepts which did not utilize solid fuel. The Subpanel endeavored to evaluate each of the concepts on a level technological playing field,'' and to identify critical technologies, issues, and early proof-of-concept experiments. The concepts included the liquid core fission, the gas core fission, the fission foil reactors, explosively driven systems, fusion, and antimatter. The results of the studies by the panel will be provided. 13 refs., 6 figs., 2 tabs.

  13. Heavy vehicle hybrid propulsion systems R and D program plan, FY 2000-2005

    SciTech Connect (OSTI)

    None

    2000-07-01T23:59:59.000Z

    This report contains the program plan and background information for the Heavy Vehicle Hybrid Propulsion R and D Program sponsored by the Department of Energy's Office of Heavy Vehicle Technologies. The program is a collaboration between industry and government established for the development of advanced hybrid-electric propulsion technology for urban cycle trucks and buses. It targets specific applications to enhance potential market success. Potential end-users are also involved.

  14. RSMASS-D nuclear thermal propulsion and bimodal system mass models

    SciTech Connect (OSTI)

    King, D.B. [DSWA/FC, Thermionic Evaluation Facility 801 University Blvd. SE Albuquerque, New Mexico (United States); Marshall, A.C. [DSWA/FC, Thermionic Evaluation Facility 801 University Blvd. SE Albuquerque, New Mexico (United States)

    1997-01-01T23:59:59.000Z

    Two relatively simple models have been developed to estimate reactor, radiation shield, and balance of system masses for a particle bed reactor (PBR) nuclear thermal propulsion concept and a cermet-core power and propulsion (bimodal) concept. The approach was based on the methodology developed for the RSMASS-D models. The RSMASS-D approach for the reactor and shield sub-systems uses a combination of simple equations derived from reactor physics and other fundamental considerations along with tabulations of data from more detailed neutron and gamma transport theory computations. Relatively simple models are used to estimate the masses of other subsystem components of the nuclear propulsion and bimodal systems. Other subsystem components include instrumentation and control (I&C), boom, safety systems, radiator, thermoelectrics, heat pipes, and nozzle. The user of these models can vary basic design parameters within an allowed range to achieve a parameter choice which yields a minimum mass for the operational conditions of interest. Estimated system masses are presented for a range of reactor power levels for propulsion for the PBR propulsion concept and for both electrical power and propulsion for the cermet-core bimodal concept. The estimated reactor system masses agree with mass predictions from detailed calculations with xx percent for both models. {copyright} {ital 1997 American Institute of Physics.}

  15. RSMASS-D nuclear thermal propulsion and bimodal system mass models

    SciTech Connect (OSTI)

    King, Donald B.; Marshall, Albert C. [DSWA/FC, Thermionic Evaluation Facility 801 University Blvd. SE Albuquerque, New Mexico (United States); DSWA/FC, Thermionic Evaluation Facility 801 University Blvd. SE Albuquerque, New Mexico (United States)

    1997-01-10T23:59:59.000Z

    Two relatively simple models have been developed to estimate reactor, radiation shield, and balance of system masses for a particle bed reactor (PBR) nuclear thermal propulsion concept and a cermet-core power and propulsion (bimodal) concept. The approach was based on the methodology developed for the RSMASS-D models. The RSMASS-D approach for the reactor and shield sub-systems uses a combination of simple equations derived from reactor physics and other fundamental considerations along with tabulations of data from more detailed neutron and gamma transport theory computations. Relatively simple models are used to estimate the masses of other subsystem components of the nuclear propulsion and bimodal systems. Other subsystem components include instrumentation and control (I and C), boom, safety systems, radiator, thermoelectrics, heat pipes, and nozzle. The user of these models can vary basic design parameters within an allowed range to achieve a parameter choice which yields a minimum mass for the operational conditions of interest. Estimated system masses are presented for a range of reactor power levels for propulsion for the PBR propulsion concept and for both electrical power and propulsion for the cermet-core bimodal concept. The estimated reactor system masses agree with mass predictions from detailed calculations with xx percent for both models.

  16. An Overview of Facilities and Capabilities to Support the Development of Nuclear Thermal Propulsion

    SciTech Connect (OSTI)

    James Werner; Sam Bhattacharyya; Mike Houts

    2011-02-01T23:59:59.000Z

    Abstract. The future of American space exploration depends on the ability to rapidly and economically access locations of interest throughout the solar system. There is a large body of work (both in the US and the Former Soviet Union) that show that Nuclear Thermal Propulsion (NTP) is the most technically mature, advanced propulsion system that can enable this rapid and economical access by its ability to provide a step increase above what is a feasible using a traditional chemical rocket system. For an NTP system to be deployed, the earlier measurements and recent predictions of the performance of the fuel and the reactor system need to be confirmed experimentally prior to launch. Major fuel and reactor system issues to be addressed include fuel performance at temperature, hydrogen compatibility, fission product retention, and restart capability. The prime issue to be addressed for reactor system performance testing involves finding an affordable and environmentally acceptable method to test a range of engine sizes using a combination of nuclear and non-nuclear test facilities. This paper provides an assessment of some of the capabilities and facilities that are available or will be needed to develop and test the nuclear fuel, and reactor components. It will also address briefly options to take advantage of the greatly improvement in computation/simulation and materials processing capabilities that would contribute to making the development of an NTP system more affordable. Keywords: Nuclear Thermal Propulsion (NTP), Fuel fabrication, nuclear testing, test facilities.

  17. DOE Vehicle Technologies Program 2009 Merit Review Report - Propulsion...

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

    7.pdf More Documents & Publications DOE Vehicle Technologies Program 2009 Merit Review Report - Lightweight Materials DOE Vehicle Technologies Program 2009 Merit Review Report -...

  18. Nuclear Technology Programs

    SciTech Connect (OSTI)

    Harmon, J.E. (ed.)

    1990-10-01T23:59:59.000Z

    This document reports on the work done by the Nuclear Technology Programs of the Chemical Technology Division, Argonne National Laboratory, in the period April--September 1988. These programs involve R D in three areas: applied physical chemistry, separation science and technology, and nuclear waste management. The work in applied physical chemistry includes investigations into the processes that control the release and transport of fission products under accident-like conditions, the thermophysical properties of selected materials in environments simulating those of fusion energy systems. In the area of separation science and technology, the bulk of the effort is concerned with developing and implementing processes for the removal and concentration of actinides from waste streams contaminated by transuranic elements. Another effort is concerned with examining the feasibility of substituting low-enriched for high-enriched uranium in the production of fission-product {sup 99}Mo. In the area of waste management, investigations are underway on the performance of materials in projected nuclear repository conditions to provide input to the licensing of the nation's high-level waste repositories.

  19. Office of Nuclear Facility Safety Programs

    Broader source: Energy.gov [DOE]

    The Office of Nuclear Facility Safety Programs establishes nuclear safety requirements related to safety management programs that are essential to the safety of DOE nuclear facilities.

  20. National Spent Nuclear Fuel Program

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

    need to safely and efficiently manage all DOE-owned spent nuclear fuel and high level waste and prepare it for disposal. The National Spent Nuclear Fuel Program is addressing...

  1. Space Nuclear Power and Propulsion - a basic Tool for the manned Exploration of the Solar System

    SciTech Connect (OSTI)

    Frischauf, Norbert; Hamilton, Booz Allen [ESA/ESTEC, Keplerlaan 1, P.O. Box 29, NL-2200 AG Noordwijk (Netherlands)

    2004-07-01T23:59:59.000Z

    Humanity has started to explore space more than 40 years ago. Numerous spacecraft have left the Earth in this endeavour, but while unmanned spacecraft were already sent out on missions, where they would eventually reach the outer limits of the Solar System, manned exploration has always been confined to the tiny bubble of the Earth's gravitational well, stretching out at maximum to our closest celestial companion - the Moon - during the era of the Apollo programme in the late 60's and early 70's. When mankind made its giant leap, the exploration of our cosmic neighbour was seen as the initial step for the manned exploration of the whole Solar System. Consequently ambitious research and development programmes were undertaken at that time to enable what seemed to be the next logical steps: the establishment of a permanent settled base on the Moon and the first manned mission to Mars in the 80's. Nuclear space power and propulsion played an important role in these entire future scenarios, hence ambitious development programmes were undertaken to make these technologies available. Unfortunately the 70's-paradigm shift in space policies did not only bring an end to the Apollo programme, but it also brought a complete halt to all of these technology programmes and confined the human presence in space to a tiny bubble including nothing more than the Earth's sphere and a mere shell of a few hundred kilometres of altitude, too small to even include the Moon. Today, after more than three decades, manned exploration of the Solar System has become an issue again and so are missions to Moon and Mars. However, studies and analyses show that all of these future plans are hampered by today's available propulsion systems and by the problematic of solar power generation at distances at and beyond of Mars, a problem, however, that can readily be solved by the utilisation of space nuclear reactors and propulsion systems. This paper intends to provide an overview on the various fission- and fusion-based Nuclear Power and Propulsion system concepts and tries to compare these systems' different working principles and technical implementations with each other. The overview and comparison will be complemented by a closer look at ongoing activities related to research and development in this area and by an outlook on what kind of systems might be employed to carry the first astronauts to Mars and beyond. (autho0008.

  2. Heavy vehicle propulsion system materials program semiannual progress report for April 1999 through September 1999

    SciTech Connect (OSTI)

    Johnson, D.R.

    2000-01-01T23:59:59.000Z

    The purpose of the Heavy Vehicle Propulsion System Materials Program is the development of materials: ceramics, intermetallics, metal alloys, and metal and ceramic coatings, to support the dieselization of class 1-3 trucks to realize a 35% fuel-economy improvement over current gasoline-fueled trucks and to support commercialization of fuel-flexible LE-55 low-emissions, high-efficiency diesel engines for class 7-8 trucks.

  3. Mars mission opportunity and transit time sensitivity for a nuclear thermal rocket propulsion application

    SciTech Connect (OSTI)

    Young, A.C.; Mulqueen, J.A.; Nishimuta, E.L.; Emrich, W.J. (George C. Marshall Space Flight Center, Marshall Space Flight Center, Alabama 35812 (United States))

    1993-01-10T23:59:59.000Z

    President George Bush's 1989 challenge to America to support the Space Exploration Initiative (SEI) of Back to the Moon and Human Mission to Mars'' gives the space industry an opportunity to develop effective and efficient space transportation systems. This paper presents stage performance and requirements for a nuclear thermal rocket (NTR) Mars transportation system to support the human Mars mission of the SEI. Two classes of Mars mission profiles are considered in developing the NTR propulsion vehicle performance and requirements. The two Mars mission classes include the opposition class and conjunction class. The opposition class mission is associated with relatively short Mars stay times ranging from 30 to 90 days and total mission duration of 350 to 600 days. The conjunction class mission is associated with much longer Mars stay times ranging from 500 to 600 days and total mission durations of 875 to 1,000 days. Vehicle mass scaling equations are used to determine the NTR stage mass, size, and performance range required for different Mars mission opportunities and for different Mars mission durations. Mission opportunities considered include launch years 2010 to 2018. The 2010 opportunity is the most demanding launch opportunity and the 2018 opportunity is the least demanding opportunity. NTR vehicle mass and size sensitivity to NTR engine thrust level, engine specific impulse, NTR engine thrust-to-weight ratio, and Mars surface payload are presented. NTR propulsion parameter ranges include those associated with NERVA, particle bed reactor (PBR), low-pressure, and ceramic-metal-type engine design.

  4. Technology Survey and Performance Scaling for the Design of High Power Nuclear Electric Power and Propulsion Systems

    E-Print Network [OSTI]

    , use of electric primary propulsion in flight systems has been limited to low-power, solar electric thruster output power are identified. Design evolutions are presented for three thrusters that would1 Technology Survey and Performance Scaling for the Design of High Power Nuclear Electric Power

  5. Heavy vehicle propulsion system materials program semiannual progress report for April 1998 thru September 1998

    SciTech Connect (OSTI)

    Johnson, D.R.

    1999-01-01T23:59:59.000Z

    The purpose of the Heavy Vehicle Propulsion System Materials Program is the development of materials: ceramics, intermetallics, metal alloys, and metal and ceramic coatings, to support the dieselization of class 1--3 trucks to realize a 35{percent} fuel-economy improvement over current gasoline-fueled trucks and to support commercialization of fuel-flexible LE-55 low-emissions, high-efficiency diesel engines for class 7--8 trucks. The Office of Transportation Technologies, Office of Heavy Vehicle Technologies (OTT OHVT) has an active program to develop the technology for advanced LE-55 diesel engines with 55{percent} efficiency and low emissions levels of 2.0 g/bhp-h NO{sub x} and 0.05 g/bhp-h particulates. The goal is also for the LE-55 engine to run on natural gas with efficiency approaching that of diesel fuel. The LE-55 program is being completed in FY 1997 and, after approximately 10 years of effort, has largely met the program goals of 55{percent} efficiency and low emissions. However, the commercialization of the LE-55 technology requires more durable materials than those that have been used to demonstrate the goals. Heavy Vehicle Propulsion System Materials will, in concert with the heavy-duty diesel engine companies, develop the durable materials required to commercialize the LE-55 technologies.

  6. Preliminary Design of a Manned Nuclear Electric Propulsion Vehicle Using Genetic Algorithms

    SciTech Connect (OSTI)

    Irwin, Ryan W. [School of Aeronautics and Astronautics, Purdue University, West Lafayette, IN 47907 (United States); Tinker, Michael L. [Spacecraft and Vehicle Systems Department, NASA Marshall Space Flight Center, Huntsville, AL 35812 (United States)

    2005-02-06T23:59:59.000Z

    Nuclear electric propulsion (NEP) vehicles will be needed for future manned missions to Mars and beyond. Candidate designs must be identified for further detailed design from a large array of possibilities. Genetic algorithms have proven their utility in conceptual design studies by effectively searching a large design space to pinpoint unique optimal designs. This research combined analysis codes for NEP subsystems with a genetic algorithm. The use of penalty functions with scaling ratios was investigated to increase computational efficiency. Also, the selection of design variables for optimization was considered to reduce computation time without losing beneficial design search space. Finally, trend analysis of a reference mission to the asteroids yielded a group of candidate designs for further analysis.

  7. Nuclear Physics Program

    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 Administration the ContributionsArms Control R&D ConsortiumNuclear Pairs

  8. Propulsion System Materials Program semiannual progress report for April 1995 through September 1995

    SciTech Connect (OSTI)

    NONE

    1996-04-01T23:59:59.000Z

    Significant accomplishments in fabricating ceramic components for the DOE, NASA, and DOD advanced heat engine programs have provided evidence that the operation of ceramic parts in high-temperature engine environments is feasible. These programs have also demonstrated that additional research is needed in materials and processing development, design methodology, and data base and life prediction before industry will have a sufficient technology base from which to produce reliable cost-effective ceramic engine components commercially. An assessment of needs was completed, and a 5-year program plan was developed with extensive input from private industry. During the course of the Propulsion System Materials Program, remarkable progress has been made in the development of reliable structural ceramics. However, further work is needed to reduce the cost of ceramics to facilitate their commercial introduction, especially in the highly cost-sensitive automotive market. To this end, the direction of the Propulsion System Materials Program is now shifting toward reducing the cost of ceramics to facilitate commercial introduction of ceramic components for near-term engine applications. In response to extensive input from industry, the plan is to extend the engine types which were previously supported to include near-term (5--10 years) applications in conventional automobile and diesel truck engines. To facilitate the rapid transfer of this technology to US industry, the major portion of the work is being done in the ceramic industry, with technological support from government laboratories, other industrial laboratories, and universities. A systematic approach to reducing the cost of components is envisioned. The work elements are as follows: economic cost modeling, ceramic machining, powder synthesis, alternative forming and densification processes, yield improvement, system design studies, standards development, low-expansion ceramics, and testing and data base development.

  9. 2013 Annual Planning Summary for the Naval Nuclear Propulsion Program |

    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 RankCombustionImprovement Awardflash2007-42attachment1.pdfmodule(EE)2012

  10. Nuclear Nonproliferation Programs | 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 Administration the ContributionsArms Control R&D Consortium

  11. Heavy vehicle propulsion system materials program: Semiannual progress report, April 1996--September 1996

    SciTech Connect (OSTI)

    Johnson, D.R.

    1997-04-01T23:59:59.000Z

    The purpose of the Heavy Vehicle Propulsion System Materials Program is the development of materials: ceramics, intermetallics, metal alloys, and metal and ceramic coatings, to support the dieselization of class 1-3 trucks to realize a 35% fuel-economy improvement over current gasoline-fueled trucks and to support commercialization of fuel-flexible LE-55 low-emissions, high-efficiency diesel engines for class 7-8 trucks. The Office of Transportation Technologies, Office of Heavy Vehicle Technologies (OTT OHVT) has an active program to develop the technology for advanced LE-55 diesel engines with 55% efficiency and low emissions levels of 2.0 g/bhp-h NO{sub x} and 0.05 g/bhp-h particulates. The goal is also for the LE-55 engine to run on natural gas with efficiency approaching that of diesel fuel. The LE-55 program is being completed in FY 1997 and, after approximately 10 years of effort, has largely met the program goals of 55% efficiency and low emissions. However, the commercialization of the LE-55 technology requires more durable materials than those that have been used to demonstrate the goals. Heavy Vehicle Propulsion System Materials will, in concert with the heavy duty diesel engine companies, develop the durable materials required to commercialize the LE-55 technologies. OTT OHVT also recognizes a significant opportunity for reduction in petroleum consumption by dieselization of pickup trucks, vans, and sport utility vehicles. Application of the diesel engine to class 1, 2, and 3 trucks is expected to yield a 35% increase in fuel economy per vehicle. The foremost barrier to diesel use in this market is emission control. Once an engine is made certifiable, subsequent challenges will be in cost; noise, vibration, and harshness (NVH); and performance. Separate abstracts have been submitted to the database for contributions to this report.

  12. DEPARTMENT OF NUCLEAR ENGINEERING ACADEMIC PROGRAM REVIEW

    E-Print Network [OSTI]

    DEPARTMENT OF NUCLEAR ENGINEERING ACADEMIC PROGRAM REVIEW MARCH 26-28, 2007 Department of Nuclear TABLES Table 2.5-1 Department of Nuclear Engineering Faculty 16 Table 2.5-2 Department of Nuclear Programs 21 Table 2.5-4 Faculty Service on Noteworthy Committees 23 Table 2.11-1 TAMU Nuclear Engineering

  13. Nuclear Explosive and Weapon Surety Program

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

    2014-08-05T23:59:59.000Z

    The Order defines the Nuclear Explosive and Weapon Surety (NEWS) Program, which was established to prevent unintended/unauthorized detonation and deliberate unauthorized use of nuclear explosives.

  14. National Nuclear Security Administration Appropriation and Program...

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

    4 National Nuclear Security Administration Appropriation and Program Summary Tables Outyear Appropriation Summary Tables FY 2012 BUDGET TABLES National Nuclear Security...

  15. Nuclear Explosive and Weapon Surety Program - DOE Directives...

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

    D, Nuclear Explosive and Weapon Surety Program by cdornburg Functional areas: Defense Nuclear Facility Safety and Health Requirement, Defense Programs, Nuclear Weapons Programs,...

  16. Lightweighting and Propulsion Materials Roadmapping Workshop...

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

    Lightweighting and Propulsion Materials Roadmapping Workshop Outbrief Lightweighting and Propulsion Materials Roadmapping Workshop Outbrief 2012 DOE Hydrogen and Fuel Cells Program...

  17. Heavy Vehicle Propulsion System Materials Program Semiannual Progress Report for October 1998 Through March 1999

    SciTech Connect (OSTI)

    Johnson, R.D.

    1999-06-01T23:59:59.000Z

    The purpose of the Heavy Vehicle Propulsion System Materials Program is the development of materials: ceramics, intermetallics, metal alloys, and metal and ceramic coatings, to support the dieselization of class 1-3 trucks to realize a 35% fuel-economy improvement over current gasoline-fueled trucks and to support commercialization of fuel-flexible LE-55 low-emissions, high-efficiency diesel engines for class 7-8 trucks. The Office of Transportation Technologies, Office of Heavy Vehicle Technologies (OIT OHVT) has an active program to develop the technology for advanced LE-55 diesel engines with 55% efficiency and low emissions levels of 2.0 g/bhp-h NOX and 0.05 g/bhp-h particulate. The goal is also for the LE-55 engine to run on natural gas with efficiency approaching that of diesel fuel. The LE-55 program is being completed in FY 1997 and, after approximately 10 years of effort, has largely met the program goals of 55% efficiency and low emissions. However, the commercialization of the LE-55 technology requires more durable materials than those that have been used to demonstrate the goals. Heavy Vehicle Propulsion System Materials will, in concert with the heavy duty diesel engine companies, develop the durable materials required to commercialize the LE-55 technologies. OIT OHVT also recognizes a significant opportunity for reduction in petroleum consumption by dieselization of pickup trucks, vans, and sport utility vehicles. Application of the diesel engine to class 1,2, and 3 trucks is expected to yield a 35% increase in fuel economy per vehicle. The foremost barrier to diesel use in this market is emission control. Once an engine is made certifiable, subsequent challenges will be in cost; noise, vibration, and harshness (NVH); and performance. The design of advanced components for high-efficiency diesel engines has, in some cases, pushed the performance envelope for materials of construction past the point of reliable operation. Higher mechanical and tribological stresses and higher temperatures of advanced designs limit the engine designer; advanced materials allow the design of components that may operate reliably at higher stresses and temperatures, thus enabling more efficient engine designs. Advanced materials also offer the opportunity to improve the emissions, NVH, and performance of diesel engines for pickup trucks, vans, and sport utility vehicles. The principal areas of research are: (1) Cost Effective High Performance Materials and Processing; (2) Advanced Manufacturing Technology; (3)Testing and Characterization; and (4) Materials and Testing Standards.

  18. Establishing nuclear facility drill programs

    SciTech Connect (OSTI)

    NONE

    1996-03-01T23:59:59.000Z

    The purpose of DOE Handbook, Establishing Nuclear Facility Drill Programs, is to provide DOE contractor organizations with guidance for development or modification of drill programs that both train on and evaluate facility training and procedures dealing with a variety of abnormal and emergency operating situations likely to occur at a facility. The handbook focuses on conducting drills as part of a training and qualification program (typically within a single facility), and is not intended to included responses of personnel beyond the site boundary, e.g. Local or State Emergency Management, Law Enforcement, etc. Each facility is expected to develop its own facility specific scenarios, and should not limit them to equipment failures but should include personnel injuries and other likely events. A well-developed and consistently administered drill program can effectively provide training and evaluation of facility operating personnel in controlling abnormal and emergency operating situations. To ensure the drills are meeting their intended purpose they should have evaluation criteria for evaluating the knowledge and skills of the facility operating personnel. Training and evaluation of staff skills and knowledge such as component and system interrelationship, reasoning and judgment, team interactions, and communications can be accomplished with drills. The appendices to this Handbook contain both models and additional guidance for establishing drill programs at the Department`s nuclear facilities.

  19. FUSION NUCLEAR SCIENCE PROGRAM & SUPPORTING FUSION NUCLEAR SCIENCE FACILITY (FNSF)

    E-Print Network [OSTI]

    FUSION NUCLEAR SCIENCE PROGRAM & SUPPORTING FUSION NUCLEAR SCIENCE FACILITY (FNSF): UPDATE · It was well recognized there were also critical materials and technology issues that needed to be addressed in order to apply the knowledge we gained about burning plasma state #12;FUSION NUCLEAR SCIENCE PROGRAM

  20. Heavy Vehicle Propulsion System Materials Program semiannual progress report for October 1996 through March 1997

    SciTech Connect (OSTI)

    NONE

    1997-07-01T23:59:59.000Z

    The purpose of the Heavy Vehicle Propulsion System Materials Program is the development of materials: ceramics, intermetallics, metal alloys, and metal and ceramic coatings, to support the dieselization of class 1-3 trucks to realize a 35% fuel-economy improvement over current gasoline-fueled trucks and to support commercialization of fuel-flexible LE-55 low-emissions, high-efficiency diesel engines for class 7-8 trucks. The design of advanced components for high-efficiency diesel engines has, in some cases, pushed the performance envelope for materials of construction past the point of reliable operation. Higher mechanical and tribological stresses and higher temperatures of advanced designs limit the engine designers; advanced materials allow the design of components that may operate reliably at higher stresses and temperatures, thus enabling more efficient engine designs. Advanced materials also offer the opportunity to improve the emissions, NVH, and performance of diesel engines for pickup trucks, vans, and sport utility vehicles. The principal areas of research are: (1) cost effective high performance materials and processing; (2) advanced manufacturing technology; (3) testing and characterization; and (4) materials and testing standards.

  1. Nuclear Explosive and Weapon Surety Program

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

    2015-01-26T23:59:59.000Z

    All nuclear explosives and nuclear explosive operations require special safety, security, and use control consideration because of the potentially unacceptable consequences of an accident or unauthorized act; therefore, a Nuclear Explosive and Weapon Surety (NEWS) Program is established to prevent unintended/unauthorized detonation and deliberate unauthorized use of nuclear explosives.

  2. Nuclear Explosive and Weapon Surety Program - DOE Directives...

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

    1E, Nuclear Explosive and Weapon Surety Program by Angela Chambers Functional areas: Defense Nuclear Facility Safety and Health Requirement, Defense Programs, Nuclear Weapons...

  3. Status of Iran's nuclear program and negotiations

    SciTech Connect (OSTI)

    Albright, David [President, Institute for Science and International Security (ISIS), 236 Massachusetts Avenue, NE 305, Washington, DC 20002 (United States)

    2014-05-09T23:59:59.000Z

    Iran's nuclear program poses immense challenges to international security. Its gas centrifuge program has grown dramatically in the last several years, bringing Iran close to a point where it could produce highly enriched uranium in secret or declared gas centrifuge plants before its breakout would be discovered and stopped. To reduce the risk posed by Iran's nuclear program, the P5+1 have negotiated with Iran short term limits on the most dangerous aspects of its nuclear programs and is negotiating long-term arrangements that can provide assurance that Iran will not build nuclear weapons. These long-term arrangements need to include a far more limited and transparent Iranian nuclear program. In advance of arriving at a long-term arrangement, the IAEA will need to resolve its concerns about the alleged past and possibly on-going military dimensions of Iran's nuclear program.

  4. Elements of a nuclear criticality safety program

    SciTech Connect (OSTI)

    Hopper, C.M.

    1995-07-01T23:59:59.000Z

    Nuclear criticality safety programs throughout the United States are quite successful, as compared with other safety disciplines, at protecting life and property, especially when regarded as a developing safety function with no historical perspective for the cause and effect of process nuclear criticality accidents before 1943. The programs evolved through self-imposed and regulatory-imposed incentives. They are the products of conscientious individuals, supportive corporations, obliged regulators, and intervenors (political, public, and private). The maturing of nuclear criticality safety programs throughout the United States has been spasmodic, with stability provided by the volunteer standards efforts within the American Nuclear Society. This presentation provides the status, relative to current needs, for nuclear criticality safety program elements that address organization of and assignments for nuclear criticality safety program responsibilities; personnel qualifications; and analytical capabilities for the technical definition of critical, subcritical, safety and operating limits, and program quality assurance.

  5. A radiological assessment of nuclear power and propulsion operations near Space Station Freedom. Contract report, January 1988-January 1990

    SciTech Connect (OSTI)

    Bolch, W.E.; Thomas, J.K.; Peddicord, K.L.; Nelson, P.; Marshall, D.T.; Busche, D.M.

    1990-03-01T23:59:59.000Z

    Scenarios were identified which involve the use of nuclear power systems in the vicinity of Space Station Freedom (SSF) and their radiological impact on the SSF crew was quantified. Several of the developed scenarios relate to the use of SSF as an evolutionary transportation node for lunar and Mars missions. In particular, radiation doses delivered to SSF crew were calculated for both the launch and subsequent return of a Nuclear Electric Propulsion (NEP) cargo vehicle and a Nuclear Thermal Rocket (NTR) personnel vehicle to low earth orbit. The use of nuclear power on co-orbiting platforms and the storage and handling issues associated with radioisotope power systems were also explored as they relate to SSF. A central philosophy in these analyses was the utilization of a radiation dose budget, defined as the difference between recommended dose limits from all radiation sources and estimated doses received by crew members from natural space radiations. Consequently, for each scenario examined, the dose budget concept was used to identify and quantify constraints on operational parameters such as launch separation distances, returned vehicle parking distances, and reactor shutdown times prior to vehicle approach. The results indicate that realistic scenarios do not exist which would preclude the use of nuclear power sources in the vicinity of SSF. The radiation dose to the SSF crew can be maintained at safe levels solely by implementing proper and reasonable operating procedures.

  6. Heavy vehicle propulsion system materials program semi-annual progress report for October 1997 through March 1998

    SciTech Connect (OSTI)

    Johnson, D.R.

    1998-06-01T23:59:59.000Z

    The purpose of the Heavy Vehicle Propulsion System materials Program is the development of materials: ceramics, intermetallics, metal alloys, and metal and ceramic coatings, to support the dieselization of class 1--3 trucks to realize a 35{percent} fuel-economy improvement over current gasoline-fueled trucks and to support commercialization of fuel-flexible LE-55 low-emissions, high-efficiency diesel engines for class 7--8 trucks. The Office of Transportation Technologies, Office of Heavy Vehicle Technologies (OTT OHVT) has an active program to develop the technology for advanced LE-55 diesel engines with 55{percent} efficiency and low emissions levels of 2.0 g/bhp-h NO{sub x} and 0.05 g/bhp-h particulates. The goal is also for the LE-55 engine to run on natural gas with efficiency approaching that of diesel fuel. The LE-55 program is being completed in FY 1997 and, after approximately 10 years of effort, has largely met the program goals of 55{percent} efficiency and low emissions. However, the commercialization of the LE-55 technology requires more durable materials than those that have been used to demonstrate the goals. Heavy Vehicle Propulsion System Materials will, in concert with the heavy-duty diesel engine companies, develop the durable materials required to commercialize the LE-55 technologies.

  7. ICENES `91:Sixth international conference on emerging nuclear energy systems. Program and abstracts

    SciTech Connect (OSTI)

    Not Available

    1991-12-31T23:59:59.000Z

    This document contains the program and abstracts of the sessions at the Sixth International Conference on Emerging Nuclear Energy Systems held June 16--21, 1991 at Monterey, California. These sessions included: The plenary session, fission session, fission and nonelectric session, poster session 1P; (space propulsion, space nuclear power, electrostatic confined fusion, fusion miscellaneous, inertial confinement fusion, {mu}-catalyzed fusion, and cold fusion); Advanced fusion session, space nuclear session, poster session 2P, (nuclear reactions/data, isotope separation, direct energy conversion and exotic concepts, fusion-fission hybrids, nuclear desalting, accelerator waste-transmutation, and fusion-based chemical recycling); energy policy session, poster session 3P (energy policy, magnetic fusion reactors, fission reactors, magnetically insulated inertial fusion, and nuclear explosives for power generation); exotic energy storage and conversion session; and exotic energy storage and conversion; review and closing session.

  8. Nuclear Spent Fuel Program Drivers

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

    was created to plan and coordinate the management of Department of Energy-owned spent nuclear fuel. It was established as a result of a 1992 decision to stop spent nuclear fuel...

  9. Nuclear Safety Research and Development Program Proposal Submittal...

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

    Nuclear Safety Research and Development Program Proposal Submittal Instructions for Fiscal Year 2015 1.0 INTRODUCTION The Nuclear Safety Research and Development (NSR&D) Program...

  10. Nuclear Safety Basis Program Review Overview and Management Oversight...

    Office of Environmental Management (EM)

    Nuclear Safety Basis Program Review During Facility Operations and Transitions Volume 4 - Nuclear Safety Basis Program Review During Facility Decommissioning and Environmental...

  11. Manpower development for new nuclear energy programs

    E-Print Network [OSTI]

    Verma, Aditi

    2012-01-01T23:59:59.000Z

    In the spring of 2012, nine countries were seriously considering embarking on nuclear energy programs, either having signed contracts with reactor vendors or having made investments for the development of infrastructure ...

  12. Nuclear Power 2010 Program: Combined Construction and Operating...

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

    Power 2010 Program: Combined Construction and Operating License & Design Certification Demonstration Projects Lessons Learned Report Nuclear Power 2010 Program: Combined...

  13. Nuclear Materials Management Program at the NNSS

    SciTech Connect (OSTI)

    ,

    2012-06-08T23:59:59.000Z

    The Nevada National Security Site (NNSS), formerly the Nevada Test Site, was established in 1951 mainly for weapons testing; because special nuclear materials (SNM) were expended during the tests, a nuclear material management program was not required. That changed in December 2004 with the receipt of Category I SNM for purposes other than weapons testing. At that time, Material Control and Accountability and Nuclear Material Management were a joint laboratory (Los Alamos and Lawrence Livermore) effort with nuclear material management being performed at the laboratories. That changed in March 2006 when the U.S. Department of Energy, National Nuclear Security Administration Nevada Site Office appointed sole responsibility to the Management and Operations (M&O) contractor, National Security Technologies, LLC (NSTec). Since 2006 the basic nuclear material management work was completed by a combination of M&O employees and subcontractors, but a true Nuclear Material Management (NMM) Program was not determined to be necessary until recently. With expanding missions and more nuclear material (NM) coming to the NNSS, it became imperative to have an organization to manage these materials; therefore, an NMM Manager was officially appointed by NSTec in 2012. In June 2011 a Gap Analysis and white paper was completed by a subcontractor; this presentation will include highlights from those documents along with our plans to resolve the gaps and stand up a functional and compliant NMM Program at the NNSS.

  14. Guidelines for Evaluation of Nuclear Facility Training Programs

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

    1995-11-22T23:59:59.000Z

    The Guidelines for Evaluation of Nuclear Facility Training Programs establish objectives and criteria for evaluating nuclear facility training programs. The guidance in this standard provides a framework for the systematic evaluation of training programs at nuclear facilities and is based, in part, on established criteria for Technical Safety Appraisals, Tiger Team Assessments, commercial nuclear industry evaluations, and the DOE Training Accreditation Program.

  15. Maintenance Management Program for DOE Nuclear Facilities

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

    2001-06-01T23:59:59.000Z

    To define the program for the management of cost-effective maintenance of Department of Energy (DOE) nuclear facilities. Guidance for compliance with this Order is contained in DOE G 433.1-1, Nuclear Facility Maintenance Management Program Guide for use with DOE O 433.1, which references Federal regulations, DOE directives, and industry best practices using a graded approach to clarify requirements and guidance for maintaining DOE-owned Government property. (Cancels DOE 4330.4B, Chapter II, Maintenance Management Program, dated 2-10-94.) Cancels DOE 4330.4B (in part). Canceled by DOE O 433.1A.

  16. Nuclear programs in India and Pakistan

    SciTech Connect (OSTI)

    Mian, Zia [Program on Science and Global Security, Princeton University, Princeton, New Jersey (United States)

    2014-05-09T23:59:59.000Z

    India and Pakistan launched their respective nuclear programs in the 1940s and 1950s with considerable foreign technical support, especially from the United States Atoms for Peace Program. The technology and training that was acquired served as the platform for later nuclear weapon development efforts that included nuclear weapon testing in 1974 and in 1998 by India, and also in 1998 by Pakistan - which had illicitly acquired uranium enrichment technology especially from Europe and received assistance from China. As of 2013, both India and Pakistan were continuing to produce fissile material for weapons, in the case of India also for nuclear naval fuel, and were developing a diverse array of ballistic and cruise missiles. International efforts to restrain the South Asian nuclear build-up have been largely set aside over the past decade as Pakistani support became central for the U.S. war in Afghanistan and as U.S. geopolitical and economic interests in supporting the rise of India, in part as a counter to China, led to India being exempted both from U.S non-proliferation laws and international nuclear trade guidelines. In the absence of determined international action and with Pakistan blocking the start of talks on a fissile material cutoff treaty, nuclear weapon programs in South Asia are likely to keep growing for the foreseeable future.

  17. Submersion Criticality Safety Analysis of Tungsten-Based Fuel for Nuclear Power and Propulsion Applications

    SciTech Connect (OSTI)

    A.E. Craft; R. C. O'Brien; S. D. Howe; J. C. King

    2014-07-01T23:59:59.000Z

    The Center for Space Nuclear Research (CSNR) is developing tungsten-encapsulated fuels for space nuclear applications. Aims to develop NTP fuels that are; Affordable Low impact on production and testing environment Producible on a large scale over suitable time period Higher-performance compared to previous graphite NTP fuel elements Space nuclear reactors remain subcritical before and during launch, and do not go critical until required by its mission. A properly designed reactor will remain subcritical in any launch abort scenario, where the reactor falls back to Earth and becomes submerged in terrestrial material. Submersion increases neutron reflection and thermalizes the neutrons, which typically increases the reactivity of the core. This effect is usually very significant for fast-spectrum reactors. This research provided a submersion criticality safety analysis for a representative tungsten/uranium oxide fueled reactor. Determine the submersion behavior of a reactor fueled by tungsten-based fuel. Considered fuel compositions with varying: Rhenium content (wt% rhenium in tungsten) Fuel loading fractions (UO2 vol%)

  18. Nuclear Explosive and Weapon Surety Program - DOE Directives...

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

    1D Admin Chg 1, Nuclear Explosive and Weapon Surety Program by Carl Sykes Functional areas: Administrative Change, Defense Nuclear Facility Safety and Health Requirement, Defense...

  19. Laboratory's role in Cold War nuclear weapons testing program...

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

    70th anniversary lecture Laboratory's role in Cold War nuclear weapons testing program focus of next 70th anniversary lecture Lab's role in the development of nuclear weapons...

  20. Nuclear Energy University Program: A Presentation to Vice Presidents...

    Office of Environmental Management (EM)

    Nuclear Energy University Program: A Presentation to Vice Presidents of Research and Development of Historically Black Colleges and Universities, given by the Office of Nuclear...

  1. Department of Energy Programmatic Spent Nuclear Fuel Management and Idaho National Engineering Laboratory Environmental Restoration and Waste Management Programs, Draft Environmental Impact Statement. Volume 1, Appendix D: Part A, Naval Spent Nuclear Fuel Management

    SciTech Connect (OSTI)

    Not Available

    1994-06-01T23:59:59.000Z

    Volume 1 to the Department of Energy`s Programmatic Spent Nuclear Fuel Management and Idaho National Engineering Laboratory Environmental Management Programs Environmental Impact Statement evaluates a range of alternatives for managing naval spent nuclear fuel expected to be removed from US Navy nuclear-powered vessels and prototype reactors through the year 2035. The Environmental Impact Statement (EIS) considers a range of alternatives for examining and storing naval spent nuclear fuel, including alternatives that terminate examination and involve storage close to the refueling or defueling site. The EIS covers the potential environmental impacts of each alternative, as well as cost impacts and impacts to the Naval Nuclear Propulsion Program mission. This Appendix covers aspects of the alternatives that involve managing naval spent nuclear fuel at four naval shipyards and the Naval Nuclear Propulsion Program Kesselring Site in West Milton, New York. This Appendix also covers the impacts of alternatives that involve examining naval spent nuclear fuel at the Expended Core Facility in Idaho and the potential impacts of constructing and operating an inspection facility at any of the Department of Energy (DOE) facilities considered in the EIS. This Appendix also considers the impacts of the alternative involving limited spent nuclear fuel examinations at Puget Sound Naval Shipyard. This Appendix does not address the impacts associated with storing naval spent nuclear fuel after it has been inspected and transferred to DOE facilities. These impacts are addressed in separate appendices for each DOE site.

  2. Progress in colloid propulsion

    E-Print Network [OSTI]

    Lpez Urdiales, Jse Mariano, 1977-

    2004-01-01T23:59:59.000Z

    In the early decades of the Space Age, a great deal of work was put into the development of the Colloid Thruster as an electric propulsion system for spacecraft. In spite of the effort by the end of the 70s the programs ...

  3. Hypersonic missile propulsion system

    SciTech Connect (OSTI)

    Kazmar, R.R.

    1998-11-01T23:59:59.000Z

    Pratt and Whitney is developing the technology for hypersonic components and engines. A supersonic combustion ramjet (scramjet) database was developed using hydrogen fueled propulsion systems for space access vehicles and serves as a point of departure for the current development of hydrocarbon scramjets. The Air Force Hypersonic Technology (HyTech) Program has put programs in place to develop the technologies necessary to demonstrate the operability, performance and structural durability of an expendable, liquid hydrocarbon fueled scramjet system that operates from Mach 4 to 8. This program will culminate in a flight type engine test at representative flight conditions. The hypersonic technology base that will be developed and demonstrated under HyTech will establish the foundation to enable hypersonic propulsion systems for a broad range of air vehicle applications from missiles to space access vehicles. A hypersonic missile flight demonstration is planned in the DARPA Affordable Rapid Response Missile Demonstrator (ARRMD) program in 2001.

  4. Maintenance Management Program for DOE Nuclear Facilities

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

    2007-02-13T23:59:59.000Z

    The Order defines the safety management program required by 10 CFR 830.204(b)(5) for maintenance and the reliable performance of Structures, Systems and Components (SSCs) that are part of the safety basis required by 10 CFR 830.202.1 at hazard category 1, 2 and 3 Department of Energy (DOE) nuclear facilities. Cancels DOE O 433.1. Canceled by DOE O 433.1B.

  5. Maintenance Management Program for DOE Nuclear Facilities

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

    2010-04-21T23:59:59.000Z

    The order defines the safety management program required by 10 CFR 830.204(b)(5) for maintenance and the reliable performance of structures, systems and components that are part of the safety basis required by 10 CFR 830.202 at hazard category 1, 2 and 3 DOE nuclear facilities. Admin Chg 1, dated 3-12-2013. Cancels DOE O 433.1A.

  6. Maintenance Management Program for DOE Nuclear Facilities

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

    2010-04-21T23:59:59.000Z

    The order defines the safety management program required by 10 CFR 830.204(b)(5) for maintenance and the reliable performance of structures, systems and components that are part of the safety basis required by 10 CFR 830.202 at hazard category 1, 2 and 3 DOE nuclear facilities. Cancels DOE O 433.1A. Admin Chg 1, dated 3-12-2013, cancels DOE O 433.1B.

  7. International Masters Program in Nuclear Security Human Capacity Building in Nuclear Security

    E-Print Network [OSTI]

    Langendoen, Koen

    1 TUDelft International Masters Program in Nuclear Security Human Capacity Building in Nuclear Security Dirk Jan van den Berg President Del2 University of Technology participants, Nuclear security requires highly skilled experts. Professionals, who are familiar

  8. India's Nuclear Energy Program : prospects The talk will begin with a brief introduction to nuclear fission

    E-Print Network [OSTI]

    Shyamasundar, R.K.

    India's Nuclear Energy Program : prospects The talk will begin with a brief introduction to nuclear posed by reactors, the accident liability laws and regulatory structure governing nuclear energy, Wednesday, Oct 29th 4:00 PM (Tea/Coffee at Seminar Hall, TCIS Colloquium India's Nuclear Energy Program

  9. Propulsion system materials program. Semiannual progress report, October 1995--March 1996

    SciTech Connect (OSTI)

    Johnson, D.R.

    1996-07-01T23:59:59.000Z

    This portion of the program is identified as program element 1.0 within the work breakdown structure (WBS). It contains five subelements: (1) Monolithics, (2) Ceramic Composites, (3) Thermal and Wear Coatings, (4) Joining, and (5) Ceramic Machining. Ceramic research conducted within the Monolithics subelement currently includes work activities on low Cost Si{sub 3}N{sub 4} powder, green state ceramic fabrication, characterization, and densification, and on structural, mechanical, and physical properties of these ceramics. Research conducted within the Ceramic Composites subelement currently includes silicon nitride and oxide-based composites, and low expansion materials. Research conducted in the Thermal and Wear Coatings subelement is currently limited to oxide-based coatings and involves coating synthesis, characterization, and determination of the mechanical and physical properties of the coatings. Research conducted in the Joining subelement currently includes studies of processes to produce strong, stable joints between zirconia ceramics and iron-base alloys. As part of an expanded effort to reduce the cost of ceramic components, a new initiative in cost effective machining has been started. A major objective of the research in the Materials and Processing program element is to systematically advance the understanding of the relationships between ceramic raw materials such as powders and reactant gases, the processing variables involved in producing the ceramic materials, and the resultant microstructures and physical and mechanical properties of the ceramic materials. Success in meeting this objective will provide U.S. companies with new or improved ways for producing economical, highly reliable ceramic components for advanced heat engines.

  10. Department of Energy Programmatic Spent Nuclear Fuel Management and Idaho National Engineering Laboratory Environmental Restoration and Waste Management Programs draft environmental impact statement. Volume 1, Appendix B: Idaho National Engineering Laboratory Spent Nuclear Fuel Management Program

    SciTech Connect (OSTI)

    Not Available

    1994-06-01T23:59:59.000Z

    The US Department of Energy (DOE) has prepared this report to assist its management in making two decisions. The first decision, which is programmatic, is to determine the management program for DOE spent nuclear fuel. The second decision is on the future direction of environmental restoration, waste management, and spent nuclear fuel management activities at the Idaho National Engineering Laboratory. Volume 1 of the EIS, which supports the programmatic decision, considers the effects of spent nuclear fuel management on the quality of the human and natural environment for planning years 1995 through 2035. DOE has derived the information and analysis results in Volume 1 from several site-specific appendixes. Volume 2 of the EIS, which supports the INEL-specific decision, describes environmental impacts for various environmental restoration, waste management, and spent nuclear fuel management alternatives for planning years 1995 through 2005. This Appendix B to Volume 1 considers the impacts on the INEL environment of the implementation of various DOE-wide spent nuclear fuel management alternatives. The Naval Nuclear Propulsion Program, which is a joint Navy/DOE program, is responsible for spent naval nuclear fuel examination at the INEL. For this appendix, naval fuel that has been examined at the Naval Reactors Facility and turned over to DOE for storage is termed naval-type fuel. This appendix evaluates the management of DOE spent nuclear fuel including naval-type fuel.

  11. 359-06/RDS/ Fusion Nuclear Science Facility and Program

    E-Print Network [OSTI]

    359-06/RDS/ rs Fusion Nuclear Science Facility and Program by R.D. Stambaugh Fusion Power, DC #12;359-06/RDS/ rs Mission of a Fusion Nuclear Science Facility (FNSF) Two Candidates: FNSF That Must Be Filled Between ITER and a DEMO * A Fusion Nuclear Science Program and Facility Fills Nearly All

  12. ASTRONAUTICS & SPACE ASTE OVERVIEW PROGRAMS AVAILABLE

    E-Print Network [OSTI]

    Rohs, Remo

    FLOWCHARTS Astronautical engineers design, build and operate space vehicles used in exploration of molecular interaction, and reconfigurable autonomous robots. PROGRAMS AVAILABLE Astronautical Engineering. Liquid- and solid-fueled rockets. Nuclear and electric propulsion. (Duplicates credit in former AME 473

  13. Nuclear and Radiological Engineering and Medical Physics Programs

    E-Print Network [OSTI]

    Weber, Rodney

    Nuclear and Radiological Engineering and Medical Physics Programs The George W. Woodruff School #12 Engineering Industry Graduate School DOE National Labs Nuclear Navy #12; 104 Operating Nuclear Power plants one of the highest among all engineers #12;Westinghouse AP1000 Areva EPR GE Nuclear ESBWR B&W m

  14. Fusion Nuclear Science and Technology ProgramFusion Nuclear Science and Technology Program Issues and Strategy for Fusion Nuclear Science Facility (FNSF)

    E-Print Network [OSTI]

    Abdou, Mohamed

    Need for Fusion Nuclear Science and Technology ProgramFusion Nuclear Science and Technology Program ­Issues and Strategy for Fusion Nuclear Science Facility (FNSF) ­Key R&D Areas to begin NOW (modeling 12, 2010 #12;Fusion Nuclear Science and Technology (FNST) FNST is the science engineering technology

  15. Enforcement Guidance Supplement 01-01: Nuclear Weapon Program...

    Office of Environmental Management (EM)

    This enforcement guidance focuses on the applicability of 10 CFR Part 830 to nuclear weapon programs and several related enforcement issues. Enforcement Guidance Supplement 01-01:...

  16. Program Objectives | National Nuclear Security Administration

    National Nuclear Security Administration (NNSA)

    National Laser Users' Facility Grant Program Program Objectives Program Objectives National Laser Users' Facility Grant Program Objectives The primary purpose of the National...

  17. Power generation from nuclear reactors in aerospace applications

    SciTech Connect (OSTI)

    English, R.E.

    1982-01-01T23:59:59.000Z

    Power generation in nuclear powerplants in space is addressed. In particular, the states of technology of the principal competitive concepts for power generation are assessed. The possible impact of power conditioning on power generation is also discussed. For aircraft nuclear propulsion, the suitability of various technologies is cursorily assessed for flight in the Earth's atmosphere. A program path is suggested to ease the conditions of first use of aircraft nuclear propulsion.

  18. Suggested Courses for ME Students Interested in Nuclear Engineering: *For information on the Nuclear Engineering Minor, see: Nuclear Engineering Program

    E-Print Network [OSTI]

    Virginia Tech

    Suggested Courses for ME Students Interested in Nuclear Engineering: *For information on the Nuclear Engineering Minor, see: Nuclear Engineering Program Required Courses: ME 4015-4016 ­ Engineering Technical Electives: NSEG 3145-3146: Fundamentals of Nuclear Engineering Application of fundamental

  19. Atomic Energy and Nuclear Materials Program (Tennessee)

    Broader source: Energy.gov [DOE]

    The Atomic Energy and Nuclear Materials section of the Tennessee Code covers all of the regulations, licenses, permits, siting requirements, and practices relevant to a nuclear energy development. ...

  20. Department of Advanced Energy Nuclear Fusion Research Education Program

    E-Print Network [OSTI]

    Yamamoto, Hirosuke

    24 Department of Advanced Energy Nuclear Fusion Research Education Program 23 8 23 to Nuclear Fusion Research Education Program 277-8561 5-1-5 1 04-7136-4092 http://www.k.u-tokyo.ac.jp/fusion: nemoto@criepi.denken.or.jp tel: 046-856-2121 12 http://www. k.u-tokyo.ac.jp/fusion-pro/ #12

  1. Department of Advanced Energy Nuclear Fusion Research Education Program

    E-Print Network [OSTI]

    Yamamoto, Hirosuke

    26 Department of Advanced Energy Nuclear Fusion Research Education Program 25 8 20) #12; 26 Guide to Nuclear Fusion Research Education Program 03-5841-6563 E-mail : ae: 050-336-27836 mail: sakai@isas.jaxa.jp tel: 050-3362-5919 , 7 12 http://www. k.u-tokyo.ac.jp/fusion

  2. UN Security Council: Iran violating ban on nuclear weapons programs

    E-Print Network [OSTI]

    UN Security Council: Iran violating ban on nuclear weapons programs 7 September 2011 Denouncement comes after International Atomic Energy Agency submits a report claiming Iran continues to make advances weaponization of its nuclear program. The United States, Germany, France and Britain joined forces in exposing

  3. Program Objectives | National Nuclear Security Administration

    National Nuclear Security Administration (NNSA)

    High Energy Density Laboratory Plasmas Program Objectives Program Objectives High Energy Density Laboratory Plasmas (HEDLP) Program Objectives Support the U.S. scientific...

  4. Nuclear Explosion Monitoring Research and Engineering Program - Strategic Plan

    SciTech Connect (OSTI)

    Casey, Leslie A. [DOE/NNSA

    2004-09-01T23:59:59.000Z

    The Department of Energy (DOE)/National Nuclear Security Administration (NNSA) Nuclear Explosion Monitoring Research and Engineering (NEM R&E) Program is dedicated to providing knowledge, technical expertise, and products to US agencies responsible for monitoring nuclear explosions in all environments and is successful in turning scientific breakthroughs into tools for use by operational monitoring agencies. To effectively address the rapidly evolving state of affairs, the NNSA NEM R&E program is structured around three program elements described within this strategic plan: Integration of New Monitoring Assets, Advanced Event Characterization, and Next-Generation Monitoring Systems. How the Program fits into the National effort and historical accomplishments are also addressed.

  5. Exercise Program | National Nuclear Security Administration

    National Nuclear Security Administration (NNSA)

    Twitter Youtube Flickr RSS People Mission Managing the Stockpile Preventing Proliferation Powering the Nuclear Navy Emergency Response Recapitalizing Our Infrastructure...

  6. ASC Program Elements | National Nuclear Security Administration

    National Nuclear Security Administration (NNSA)

    Twitter Youtube Flickr RSS People Mission Managing the Stockpile Preventing Proliferation Powering the Nuclear Navy Emergency Response Recapitalizing Our Infrastructure...

  7. Program Activities | National Nuclear Security Administration

    National Nuclear Security Administration (NNSA)

    Twitter Youtube Flickr RSS People Mission Managing the Stockpile Preventing Proliferation Powering the Nuclear Navy Emergency Response Recapitalizing Our Infrastructure...

  8. Stewardship Science Academic Programs Annual | National Nuclear...

    National Nuclear Security Administration (NNSA)

    Twitter Youtube Flickr RSS People Mission Managing the Stockpile Preventing Proliferation Powering the Nuclear Navy Emergency Response Recapitalizing Our Infrastructure...

  9. GTRI's Convert program | National Nuclear Security Administration

    National Nuclear Security Administration (NNSA)

    Twitter Youtube Flickr RSS People Mission Managing the Stockpile Preventing Proliferation Powering the Nuclear Navy Emergency Response Recapitalizing Our Infrastructure...

  10. Plutonium Disposition Program | National Nuclear Security Administrati...

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

    Disposition Plutonium Disposition Program Plutonium Disposition Program The U.S.-Russia Plutonium Management and Disposition Agreement (PMDA), which entered into force on...

  11. Hispanic Student Programs | National Nuclear Security Administration

    National Nuclear Security Administration (NNSA)

    Student Programs Hispanic Student Programs Universities across the country host high school students participating in the Hispanic Youth Symposium. Please visit the Hispanic...

  12. Program Information | National Nuclear Security Administration

    National Nuclear Security Administration (NNSA)

    and Operating (M&O) Contract Competition Program Information Program Information FY 2015 Performance Evaluation Plan (PEP) FY 2013 Performance Evaluation Report (PER)...

  13. SciTech Connect: The Soviet program for peaceful uses of nuclear...

    Office of Scientific and Technical Information (OSTI)

    The Soviet program for peaceful uses of nuclear explosions Citation Details In-Document Search Title: The Soviet program for peaceful uses of nuclear explosions You are...

  14. Training program requirements for remote equipment operators in nuclear facilities

    SciTech Connect (OSTI)

    Palau, G.L.; Auclair, K.D.

    1986-01-01T23:59:59.000Z

    One of the most neglected areas in the engineering development of remotely operated equipment applications in nuclear environments is the planning of adequate training programs for the equipment operators. Remote equipment accidents cannot be prevented solely by engineered safety features on the equipment. As a result of the experiences in using remote equipment in the recovery effort at Three Mile Island Unit 2 (TMI-2), guidelines for the development of remote equipment operator training programs have been generated. The result is that a successful education and training program can create an environment favorable to the safe and effective implementation of a remote equipment program in a nuclear facility.

  15. Radiological Assistance Program | National Nuclear Security Administra...

    National Nuclear Security Administration (NNSA)

    (trained personnel and equipment) to evaluate, assess, advise, isotopically identify, search for, and assist in the mitigation of actual or perceived nuclear or radiological...

  16. Department of Advanced Energy Nuclear Fusion Research Education Program

    E-Print Network [OSTI]

    Yamamoto, Hirosuke

    23 Department of Advanced Energy Nuclear Fusion Research Education Program 22 8 24) (1) (2) (3) (4) (5) (6) (7) (8) #12;- 7 - 23 Guide to Nuclear Fusion Research Education@criepi.denken.or.jp tel: 046-856-2121 12 http://www. k.u-tokyo.ac.jp/fusion-pro/ #12;- 3 - (1) TOEFL TOEIC

  17. Department of Advanced Energy Nuclear Fusion Research Education Program

    E-Print Network [OSTI]

    Yamamoto, Hirosuke

    25 Department of Advanced Energy Nuclear Fusion Research Education Program 24 8 21.Yasuhiro@jaxa.jp tel: 050-336-27836 mail: sakai@isas.jaxa.jp tel: 050-3362-5919 12 http://www. k.u-tokyo.ac.jp/fusion 15 (1) (2) (1) (2) (3) (4) (5) (6) (7) (8) (9) #12;- 8 - 25 Guide to Nuclear

  18. Ongoing Space Nuclear Systems Development in the United States

    SciTech Connect (OSTI)

    S. Bragg-Sitton; J. Werner; S. Johnson; Michael G. Houts; Donald T. Palac; Lee S. Mason; David I. Poston; A. Lou Qualls

    2011-10-01T23:59:59.000Z

    Reliable, long-life power systems are required for ambitious space exploration missions. Nuclear power and propulsion options can enable a bold, new set of missions and introduce propulsion capabilities to achieve access to science destinations that are not possible with more conventional systems. Space nuclear power options can be divided into three main categories: radioisotope power for heating or low power applications; fission power systems for non-terrestrial surface application or for spacecraft power; and fission power systems for electric propulsion or direct thermal propulsion. Each of these areas has been investigated in the United States since the 1950s, achieving various stages of development. While some nuclear systems have achieved flight deployment, others continue to be researched today. This paper will provide a brief overview of historical space nuclear programs in the U.S. and will provide a summary of the ongoing space nuclear systems research, development, and deployment in the United States.

  19. Collaborative development of Estonian nuclear master's program

    SciTech Connect (OSTI)

    Tkaczyk, A. H.; Kikas, A.; Realo, E.; Kirm, M.; Kiisk, M.; Isakar, K.; Suursoo, S.; Koch, R.; Feldbach, E.; Lushchik, A.; Reivelt, K. [Inst. of Physics, Univ. of Tartu, Riia 142, Tartu 51014 (Estonia)

    2012-07-01T23:59:59.000Z

    In 2009 Estonia approved the National Development Plan for the Energy Sector, including the nuclear energy option. This can be realized by construction of a nuclear power plant (NPP) in Estonia or by participation in neighboring nuclear projects (e.g., Lithuania and/or Finland). Either option requires the availability of competent personnel. It is necessary to prepare specialists with expertise in all aspects related to nuclear infrastructure and to meet workforce needs (e.g. energy enterprises, public agencies, municipalities). Estonia's leading institutions of higher education and research with the support of the European Social Fund have announced in this context a new nuclear master's curriculum to be developed. The language of instruction will be English. (authors)

  20. Nonproliferation Graduate Program | National Nuclear Security...

    National Nuclear Security Administration (NNSA)

    about the program and application information and deadlines, please visit the NGP web site off site link or call Program Manager Phyllis B. Byrd at (202) 586-2061 or e-mail...

  1. 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.

  2. Nuclear Explosive and Weapon Surety Program

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

    2001-08-06T23:59:59.000Z

    This Order provides requirements and responsibilities to prevent unintended/unauthorized detonation and deliberate unauthorized use of nuclear explosives. Cancels DOE O 452.1A. Canceled by DOE O 452.1C.

  3. Nuclear Explosive and Weapon Surety Program

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

    1997-01-17T23:59:59.000Z

    This Order provides requirements and responsibilities to prevent unintended/unauthorized detonation and deliberate unauthorized use of nuclear explosives. Cancels DOE O 452.1. Canceled by DOE O 452.1B.

  4. AGS fixed target program with nuclear beams

    SciTech Connect (OSTI)

    Foley, K.J.

    1984-01-01T23:59:59.000Z

    The recent approval of the beam transfer line from the Tandem Van de Graaf to the AGS signals the advent of a new era of Nuclear and Particle Physics at BNL. High Energy nuclear beams are expected to be available for experiments in 1986. I will discuss the direct link between the Tandems and the AGS. Two other proposed projects, the Relativistic Heavy Ion Collider and the Synchrotron Booster, are discussed in another presentation to this conference.

  5. Nuclear Explosive and Weapon Surety Program

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

    2009-04-14T23:59:59.000Z

    This Order provides requirements and responsibilities to prevent unintended/unauthorized detonation and deliberate unauthorized use of nuclear explosives. Cancels DOE O 452.1C. Admin Chg 1, dated 7-10-13, cancels DOE O 452.1D.

  6. Program Requirements | National Nuclear Security Administration

    National Nuclear Security Administration (NNSA)

    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) "ofEarlyEnergyDepartmentNational Nuclearhas 'Natitude' |Requests | National Nuclear

  7. Support of the Iraq nuclear facility dismantlement and disposal program

    SciTech Connect (OSTI)

    Coates, Roger [International Atomic Energy Agency - IAEA, Wagramer Strasse 5, P.O. Box 100 - 1400 Vienna (Austria); Cochran, John; Danneels, Jeff [Sandia National Laboratories (United States); Chesser, Ronald; Phillips, Carlton; Rogers, Brenda [Center for Environmental Radiation Studies, Texas Tech University, Lubbock, TX 79409 (United States)

    2007-07-01T23:59:59.000Z

    Available in abstract form only. Full text of publication follows: Iraq's former nuclear facilities contain large quantities of radioactive materials and radioactive waste. The Iraq Nuclear Facility Dismantlement and Disposal Program (the Iraq NDs Program) is a new program to decontaminate and permanently dispose of radioactive wastes in Iraq. The NDs Program is led by the Government of Iraq, under International Atomic Energy Agency (IAEA) auspices, with guidance and assistance from a number of countries. The U.S. participants include Texas Tech University and Sandia National Laboratories. A number of activities are ongoing under the broad umbrella of the Iraq NDs Program: drafting a new nuclear law that will provide the legal basis for the cleanup and disposal activities; assembly and analysis of existing data; characterization of soil contamination; bringing Iraqi scientists to the world's largest symposium on radioactive waste management; touring U.S. government and private sector operating radwaste disposal facilities in the U.S., and hosting a planning workshop on the characterization and cleanup of the Al-Tuwaitha Nuclear Facility. (authors)

  8. Nonproliferation Graduate Program | National Nuclear Security

    National Nuclear Security Administration (NNSA)

    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) "ofEarlyEnergyDepartmentNationalRestart of the Review ofElectronic InputNuclearNature of

  9. OFFICE OF RIVER PROTECTION NUCLEAR WASTE PROGRAM

    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 Administration the ContributionsArms Control R&DNuclear fuel recycling inNewsTimSF-428S Supplemental

  10. Defense Programs | National Nuclear Security Administration

    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 May JunDatastreamsmmcrcalgovInstrumentsruc DocumentationP-Series to UserProduct: CrudeOffice ofINLNuclear Security | National Nuclear|

  11. Environmental Program Services Contract | National Nuclear Security

    National Nuclear Security Administration (NNSA)

    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) "ofEarlyEnergyDepartmentNational NuclearhasAdministration77Nuclear Security Administration

  12. Life Extension Programs | National Nuclear Security Administration

    National Nuclear Security Administration (NNSA)

    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) "ofEarlyEnergyDepartmentNational NuclearhasAdministration77NuclearSecurityAdministrator |Life Extension

  13. Program Objectives | National Nuclear Security Administration

    National Nuclear Security Administration (NNSA)

    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) "ofEarlyEnergyDepartmentNational Nuclearhas 'Natitude' |Requests | National Nuclear SecuritySystem High

  14. Program Objectives | National Nuclear Security Administration

    National Nuclear Security Administration (NNSA)

    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) "ofEarlyEnergyDepartmentNational Nuclearhas 'Natitude' |Requests | National Nuclear SecuritySystem High

  15. Program Objectives | National Nuclear Security Administration

    National Nuclear Security Administration (NNSA)

    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) "ofEarlyEnergyDepartmentNational Nuclearhas 'Natitude' |Requests | National Nuclear SecuritySystem

  16. Student Career Experience Program | National Nuclear Security

    National Nuclear Security Administration (NNSA)

    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 ofDepartmentStewardship ScienceAdministration | National Nuclear Security

  17. Student Temporary Employment Program | National Nuclear Security

    National Nuclear Security Administration (NNSA)

    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 ofDepartmentStewardship ScienceAdministration | National Nuclear SecurityJobs

  18. Author's personal copy Canada's program on nuclear hydrogen production

    E-Print Network [OSTI]

    Naterer, Greg F.

    for hydrogen as a clean energy carrier is a sustainable, low-cost method of producing it in large capacities al. [1]. Hydrogen is used widely by petrAuthor's personal copy Canada's program on nuclear hydrogen production and the thermochemical Cue

  19. ASC Program Elements | National Nuclear Security Administration

    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 May JunDatastreamsmmcrcalgovInstrumentsruc Documentation RUCProductstwrmrAre the Effects of Global Warming?8DepartmentNewsletters |Program

  20. Minority Serving Institutions Internship Program | National Nuclear

    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 MayAtmospheric Optical Depth7-1D: VegetationEquipment SurfacesResource Program PreliminaryA3,0 AlabamaYearEnergy Minority

  1. international programs | National Nuclear Security Administration

    National Nuclear Security Administration (NNSA)

    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) "ofEarlyEnergyDepartmentNational NuclearhasAdministration goSecuritycdns ||fors |hrp |exercises |programs

  2. Exercise Program | National Nuclear Security Administration

    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 May JunDatastreamsmmcrcalgovInstrumentsruc DocumentationP-Series toESnet4:Epitaxial Thin Film XRDEvanExecutive DirectorDOEExercise Program

  3. Advanced Propulsion Technology Strategy

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

    Alternative Sources) Hydrogen Time ADVANCED PROPULSION TECHNOLOGY STRATEGY DOWNSIZED TURBO GAS ENGINE CHEVROLET CRUZE 1.4L TURBO ECOTEC Downsized SIDI Turbo Boosting HCCI -...

  4. Nuclear waste treatment program. Annual report for FY 1985

    SciTech Connect (OSTI)

    Powell, J.A. (ed.)

    1986-04-01T23:59:59.000Z

    Two of the US Department of Energy's (DOE) nuclear waste management-related goals are: (1) to ensure that waste management is not an obstacle to the further deployment of light-water reactors (LWR) and the closure of the nuclear fuel cycle and (2) to fulfill its institutional responsibility for providing safe storage and disposal of existing and future nuclear wastes. As part of its approach to achieving these goals, the Office of Terminal Waste Disposal and Remedial Action of DOE established what is now called the Nuclear Waste Treatment Program (NWTP) at the Pacific Northwest Laboratory (PNL) during the second half of FY 1982. To support DOE's attainment of its goals, the NWTP is to provide (1) documented technology necessary for the design and operation of nuclear waste treatment facilities by commercial enterprises as part of a licensed waste management system and (2) problem-specific treatment approaches, waste form and treatment process adaptations, equipment designs, and trouble-shooting assistance, as required, to treat existing wastes. This annual report describes progress during FY 1985 toward meeting these two objectives. The detailed presentation is organized according to the task structure of the program.

  5. Update on DOEs Nuclear Energy University Program

    SciTech Connect (OSTI)

    M. J. Lambregts

    2009-04-01T23:59:59.000Z

    The Center for Advanced Energy Studies (CAES) Nuclear Energy University Program Office assists the U.S. Department of Energy Office of Nuclear Energy (DOE-NE) by administering its University Program. To promote accountable relationships between universities and the TIOs/TDOs, a process was designed and administered which includes two competitive Requests for Proposals (RFPs) and two FOAs in the following areas: (1)Research and Development Grants, (2)Infrastructure improvement, and (3)Scholarships and Fellowships. NEUP will also host periodic reviews of university mission-specific R&D that document progress, reinforce accountability, and assess return on investment; sponsor workshops that inform universities of the Departments research needs to facilitate continued alignment of university R&D with NE missions; and conduct communications activities that foster stakeholder trust, serve as a catalyst for accomplishing NEUP objectives, and provide national visibility of NEUP activities and accomplishments. Year to date efforts to achieve these goals will be discussed.

  6. Nuclear Criticality Safety Application Guide: Safety Analysis Report Update Program

    SciTech Connect (OSTI)

    Not Available

    1994-02-01T23:59:59.000Z

    Martin Marietta Energy Systems, Inc. (MMES) is committed to performing and documenting safety analyses for facilities it manages for the Department of Energy (DOE). Safety analyses are performed to identify hazards and potential accidents; to analyze the adequacy of measures taken to eliminate, control, or mitigate hazards; and to evaluate potential accidents and determine associated risks. Safety Analysis Reports (SARs) are prepared to document the safety analysis to ensure facilities can be operated safely and in accordance with regulations. Many of the facilities requiring a SAR process fissionable material creating the potential for a nuclear criticality accident. MMES has long had a nuclear criticality safety program that provides the technical support to fissionable material operations to ensure the safe processing and storage of fissionable materials. The guiding philosophy of the program has always been the application of the double-contingency principle, which states: {open_quotes}process designs shall incorporate sufficient factors of safety to require at least two unlikely, independent, and concurrent changes in process conditions before a criticality accident is possible.{close_quotes} At Energy Systems analyses have generally been maintained to document that no single normal or abnormal operating conditions that could reasonably be expected to occur can cause a nuclear criticality accident. This application guide provides a summary description of the MMES Nuclear Criticality Safety Program and the MMES Criticality Accident Alarm System requirements for inclusion in facility SARs. The guide also suggests a way to incorporate the analyses conducted pursuant to the double-contingency principle into the SAR. The prime objective is to minimize duplicative effort between the NCSA process and the SAR process and yet adequately describe the methodology utilized to prevent a nuclear criticality accident.

  7. Heatpipe space power and propulsion systems

    SciTech Connect (OSTI)

    Houts, M.G.; Poston, D.I.; Ranken, W.A.

    1995-07-01T23:59:59.000Z

    Safe, reliable, low-mass space power and propulsion systems could have numerous civilian and military applications. This paper discusses two fission-powered concepts: the Heatpipe Power System (HPS) that provides power only, and the Heatpipe Bimodal System (HBS) that provides both power and thermal propulsion. Both concepts have 10 important features. First, only existing technology and recently tested fuel forms are used. Second, fuel can be removed whenever desired, greatly facilitating system fabrication and handling. Third, full electrically heated system testing is possible, with minimal operations required to replace the heaters with fuel and ready the system for launch. Fourth, the systems are passively subcritical during launch accidents. Fifth, a modular approach is used, and most technical issues can be resolved with inexpensive module tests. Sixth, bonds between dissimilar metals are minimized. Seventh, there are no single point failures during power mode operation. Eighth, fuel burnup rate is quite low to help ensure greater than 10-year system life. Ninth, there are no pumped coolant loops, and the systems can be shut down and restarted without coolant freeze/thaw concerns. Finally, a full ground nuclear test is not needed, and development costs will be low. The baseline HPS uses SNAP-10A-style thermoelectric power converters to produce 5 kWe at a system mass of about 500 kg. The unicouple thermoelectric converters have a hot shoe temperature of 1275 K and reject waste heat at 775 K. This type of thermoelectric converter has been used extensively by the space program, demonstrating an operational lifetime of decades. At higher thermal power, the same core can produce over 10 kWe using thermoelectric converters, and over 50 kWe using advanced power conversion systems.

  8. Review of the ISTC innovative nuclear programs (information review)

    SciTech Connect (OSTI)

    Tocheny, L. V. [ISTC - International Science and Technology Center, Moscow (Russian Federation)

    2006-07-01T23:59:59.000Z

    The information will be included in the review, with special attention on details of corresponding experimental programs: Novel reactor concepts, fit with GIF and INPRO: Supercritical Pressure Water aspects, Heavy metals (Lead, Lead-Bismuth) technology, HTGR critical modeling, engineering. Molten salts. Reactor data benchmarking, Accelerator Driven Systems (experimental modelling), Nuclear data measurements, Severe accident study (corium modelling, QUENCH, Chernobyl), Experimental Analysis of Hydraulically Induced Vibrations in Compact Curling Tube Steam Generators. (authors)

  9. Nuclear waste treatment program: Annual report for FY 1987

    SciTech Connect (OSTI)

    Brouns, R.A.; Powell, J.A. (comps.)

    1988-09-01T23:59:59.000Z

    Two of the US Department of Energy's (DOE) nuclear waste management-related goals are to ensure that waste management is not an obstacle to the further development of light-water reactors and the closure of the nuclear fuel cycle and to fulfill its institutional responsibility for providing safe storage and disposal of existing and future nuclear wastes. As part of its approach to achieving these goals, the Office of Remedial Action and Waste Technology of DOE established what is now called the Nuclear Waste Treatment Program (NWTP) at the Pacific Northwest Laboratory during the second half of FY 1982. To support DOE's attainment of its goals, the NWTP is to provide technology necessary for the design and operation of nuclear waste treatment facilities by commercial enterprises as part of a licensed waste management system and problem-specific treatment approaches, waste form and treatment process adaptations, equipment designs, and trouble-shooting assistance, as required to treat existing wastes. This annual report describes progress during FY 1987 towards meeting these two objectives. 24 refs., 59 figs., 24 tabs.

  10. Nye County, Nevada 1992 nuclear waste repository program: Program overview. Final report

    SciTech Connect (OSTI)

    NONE

    1998-07-01T23:59:59.000Z

    The purpose of this document is to provide an overview of the Nye County FY92 Nuclear Waste Repository Program (Program). Funds to pay for Program costs will come from the Federal Nuclear Waste Fund, which was established under the Nuclear Waste Policy Act of 1982 (NWPA). In early 1983, the Yucca Mountain was identified as a potentially suitable site for the nation`s first geologic repository for spent reactor fuel and high-level radioactive waste. Later that year, the Nye County Board of County Commissioners (Board) established the capability to monitor the Federal effort to implement the NWPA and evaluate the potential impacts of repository-related activities on Nye County. Over the last eight years, the County`s program has grown in complexity and cost in order to address DOE`s evolving site characterization studies, and prepare for the potential for facility construction and operation. Changes were necessary as well, in response to Congress`s redirection of the repository program specified in the amendments, to the NWPA approved in 1987. In early FY 1991, the County formally established a project office to plan and implement its program of work. The Repository Project Office`s (RPO) mission and functions are provided in Section 2.0. The RPO organization structure is described in Section 3.0.

  11. DHS National Technical Nuclear Forensics Program FY 10 Summary Report: Graduate Mentoring Assistance Program (GMAP)

    SciTech Connect (OSTI)

    Martha R. Finck Ph.D.

    2011-10-01T23:59:59.000Z

    This program provides practical training to DHS graduate fellows in the DOE laboratory complex. It involves coordinating students, their thesis advisors, and their laboratory project mentors in establishing a meaningful program of research which contributes to the graduate student's formation as a member of the nuclear forensics community. The summary report details the student/mentor experience and future plans after the first summer practicum. This program provides practical training to DHS graduate fellows in the DOE laboratory complex. It involves coordinating students, their thesis advisors, and their laboratory project mentors in establishing a meaningful program of research which contributes to the graduate student's formation as a member of the nuclear forensics community. This final written report includes information concerning the overall mentoring experience, including benefits (to the lab, the mentors, and the students), challenges, student research contributions, and lab mentor interactions with students home universities. Idaho National Laboratory hosted two DHS Nuclear Forensics graduate Fellows (nuclear engineering) in summer 2011. Two more Fellows (radiochemistry) are expected to conduct research at the INL under this program starting in 2012. An undergraduate Fellow (nuclear engineering) who worked in summer 2011 at the laboratory is keenly interested in applying for the NF Graduate Fellowship this winter with the aim of returning to INL. In summary, this program appears to have great potential for success in supporting graduate level students who pursue careers in nuclear forensics. This relatively specialized field may not have been an obvious choice for some who have already shown talent in the traditional areas of chemistry or nuclear engineering. The active recruiting for this scholarship program for candidates at universities across the U.S. brings needed visibility to this field. Not only does this program offer critical practical training to these students, it brings attention to a very attractive field of work where young professionals are urgently required in order for the future. The effectiveness of retaining such talent remains to be seen and may be primarily controlled by the availability of DOE laboratory research funding in this field in the years to come.

  12. Nuclear proliferation and civilian nuclear power. Report of the Nonproliferation Alternative Systems Assessment Program. Volume II. Proliferation resistance

    SciTech Connect (OSTI)

    Not Available

    1980-06-01T23:59:59.000Z

    The purpose of this volume is limited to an assessment of the relative effects that particular choices of nuclear-power systems, for whatever reasons, may have on the possible spread of nuclear-weapons capabilities. This volume addresses the concern that non-nuclear-weapons states may be able to initiate efforts to acquire or to improve nuclear-weapons capabilities through civilian nuclear-power programs; it also addresses the concern that subnational groups may obtain and abuse the nuclear materials or facilities of such programs, whether in nuclear-weapons states (NWS's) or nonnuclear-weapons states (NNW's). Accordingly, this volume emphasizes one important factor in such decisions, the resistance of nuclear-power systems to the proliferation of nuclear-weapons capabilities.

  13. Nuclear Technology Programs semiannual progress report, April-- September 1990

    SciTech Connect (OSTI)

    Harmon, J.E. [ed.

    1992-06-01T23:59:59.000Z

    This document reports on the work done by the Nuclear Technology Programs of the Chemical Technology Division, Argonne National Laboratory, in the period April--September 1990. These programs involve R&D in three areas: applied physical chemistry, separation science and technology, and nuclear waste management. The work in applied physical chemistry includes investigations into the processes that control the release and transport of fission products under accident-like conditions in a light water reactor, the thermophysical properties of the metal fuel in the Integral Fast Reactor, and the properties of selected materials in environments simulating those of fusion energy systems. In the area of separation science and technology, the bulk of the effort is concerned with developing and implementing processes for the removal and concentration of actinides from waste streams contaminated by transuranic elements. In the area of waste management, investigations are underway on the performance of materials in projected nuclear repository conditions to provide input to the licensing of the nation`s high-level waste repositories.

  14. Nuclear Technology Programs semiannual progress report, April-- September 1990

    SciTech Connect (OSTI)

    Harmon, J.E. (ed.)

    1992-06-01T23:59:59.000Z

    This document reports on the work done by the Nuclear Technology Programs of the Chemical Technology Division, Argonne National Laboratory, in the period April--September 1990. These programs involve R D in three areas: applied physical chemistry, separation science and technology, and nuclear waste management. The work in applied physical chemistry includes investigations into the processes that control the release and transport of fission products under accident-like conditions in a light water reactor, the thermophysical properties of the metal fuel in the Integral Fast Reactor, and the properties of selected materials in environments simulating those of fusion energy systems. In the area of separation science and technology, the bulk of the effort is concerned with developing and implementing processes for the removal and concentration of actinides from waste streams contaminated by transuranic elements. In the area of waste management, investigations are underway on the performance of materials in projected nuclear repository conditions to provide input to the licensing of the nation's high-level waste repositories.

  15. Nuclear Technology Programs semiannual progress report, October 1988--March 1989

    SciTech Connect (OSTI)

    Harmon, J.E. [ed.

    1990-12-01T23:59:59.000Z

    This document reports on the work done by the Nuclear Technology Programs of the Chemical Technology Division, Argonne National Laboratory, in the period October 1988--March 1989. These programs involve R&D in three areas: applied physical chemistry, separation science and technology, and nuclear waste management. The work in applied physical chemistry includes investigations into the processes that control the release and transport of fission products under accident-like conditions, the thermophysical properties of metal fuel and blanket materials of the Integral Fast Reactor, and the properties of selected materials in environments simulating those of fusion energy systems. In the area of separation science and technology, the bulk of the effort is concerned with developing and implementing processes for the removal and concentration of actinides from waste streams contaminated by transuranic elements. Another effort is concerned with examining the feasibility of substituting low-enriched for high-enriched uranium in the production of fission product {sup 99}Mo. In the area of waste management, investigations are underway on the performance of materials in projected nuclear repository conditions to provide input to the licensing of the nation`s high-level waste repositories. 127 refs., 76 figs., 103 tabs.

  16. Nuclear technology programs; Semiannual progress report, October 1989--March 1990

    SciTech Connect (OSTI)

    Harmon, J.E. [ed.

    1992-01-01T23:59:59.000Z

    This document reports on the work done by the Nuclear Technology Programs of the Chemical Technology Division, Argonne National Laboratory, in the period October 1989--March 1990. These programs involve R&D in three areas: applied physical chemistry, separation science and technology, and nuclear waste management. The work in applied physical chemistry includes investigations into the processes that control the release and transport of fission products under accident-like conditions, the thermophysical properties of metal fuel and blanket materials of the Integral Fast Reactor, and the properties of selected materials in environments simulating those of fusion energy systems. In the area of separation science and technology, the bulk of the effort is concerned with developing and implementing processes for the removal and concentration of actinides from waste streams contaminated by transuranic elements. Another effort is concerned water waste stream generated in production of 2,4,6-trinitrotoluene. In the area of waste management, investigations are underway on the performance of materials in projected nuclear repository conditions to provide input to the licensing of the nation`s high-level waste repositories.

  17. Nuclear technology programs. Semiannual progress report, April--September 1991

    SciTech Connect (OSTI)

    Not Available

    1993-07-01T23:59:59.000Z

    This document reports on the work done by the Nuclear Technology Programs of the Chemical Technology Division, Argonne National Laboratory, in the period April through September 1991. These programs involve R & D in three areas: applied physical chemistry, separation science and technology, and nuclear waste management. The work in applied physical chemistry includes investigations into the processes that control the release and transport of fission products under accident-like conditions in a light water reactor, the thermophysical properties of the metal fuel in the Integral Fast Reactor, and the properties of selected materials in environments simulating those of fusion energy systems. In the area of separation science and technology, the bulk of the effort is concerned with developing and implementing processes for the removal and concentration of actinides from waste streams contaminated by transuranic elements. In the area of waste management, investigations are underway on the performance of materials in projected nuclear repository conditions to provide input to the licensing of the nation`s high-level waste repositories.

  18. Nuclear Technology Programs semiannual progress report, October 1990--March 1991

    SciTech Connect (OSTI)

    NONE

    1992-12-01T23:59:59.000Z

    This document reports on the work done by the Nuclear Technology Programs of the Chemical Technology Division, Argonne National Laboratory, in the period October 1990--March 1991. These programs involve R&D in three areas: applied physical chemistry, separation science and technology, and nuclear waste management. The work in applied physical chemistry includes investigations into the processes that control the release and transpose of fission products under accident-like conditions in a light water reactor, the thermophysical properties of the metal fuel in the Integral Fast Reactor, and the properties of selected materials in environments simulating those of fusion energy systems. In the area of separation science and technology, the bulk of the effort is concerned with developing and implementing processes for the removal and concentration of actinides from waste streams contaminated by transuranic elements. In the area of waste management, investigations are underway on the performance of materials in projected nuclear repository conditions to provide input to the licensing of the nation`s high-level waste repositories.

  19. Office of Nuclear Energy Knowledge Management Program Situational Analysis Report

    SciTech Connect (OSTI)

    Kimberlyn C. Mousseau

    2011-12-01T23:59:59.000Z

    Knowledge management (KM) has been a high priority for the Department of Energy (DOE) Office of Nuclear Energy (NE) for the past several years. NE Programs are moving toward well-established knowledge management practices and a formal knowledge management program has been established. Knowledge management is being practiced to some level within each of the NE programs. Although it continues to evolve as NE programs evolve, a formal strategic plan that guides the implementation of KM has been developed. Despite the acceptance of KM within DOE NE, more work is necessary before the NE KM program can be considered fully successful. Per Dr. David J. Skyrme[1], an organization typically moves through the following evolutionary phases: (1) Ad-hoc - KM is being practiced to some level in some parts of the organization; (2) Formal - KM is established as a formal project or program; (3) Expanding - the use of KM as a discipline grows in practice across different parts of the organization; (4) Cohesive - there is a degree of coordination of KM; (5) Integrated - there are formal standards and approaches that give every individual access to most organizational knowledge through common interfaces; and (6) Embedded - KM is part-and-parcel of everyday tasks; it blends seamlessly into the background. According to the evolutionary phases, the NE KM program is operating at the two lower levels, Ad-hoc and Formal. Although KM is being practiced to some level, it is not being practiced in a consistent manner across the NE programs. To be fully successful, more emphasis must be placed on establishing KM standards and processes for collecting, organizing, sharing and accessing NE knowledge. Existing knowledge needs to be prioritized and gathered on a routine basis, its existence formally recorded in a knowledge inventory. Governance to ensure the quality of the knowledge being used must also be considered. For easy retrieval, knowledge must be organized according to a taxonomy that mimics nuclear energy programs. Technologies need to be established to make accessing the knowledge easier for the user. Finally, knowledge needs to be used as part of a well defined work process.

  20. An overview of the Nuclear Materials Focus Area research program

    SciTech Connect (OSTI)

    ROBERSON,GARY D.; POLANSKY,GARY F.; OSBORNE,KEN K.; RANDALL,VIRGINIA

    2000-02-25T23:59:59.000Z

    The Nuclear Material Focus Area (NMFA) is responsible for providing comprehensive needs identification, integration of technology research and development activities, and technology deployment for stabilization, packaging, and interim storage of surplus nuclear materials within the DOE complex. The NMFA was chartered in April 1999 by the Office of Science and Technology (OST), an organizational component of the US Department of Energy's (DOE) Office of Environmental Management (EM). OST manages a national program to conduct basic and applied research, and technology development, demonstration, and deployment assistance that is essential to completing a timely and cost-effective cleanup of the DOE nuclear weapons complex. DOE/EM provides environmental research results, as well as cleanup technologies and systems, to meet high-priority end-user needs, reduce EM's major cost centers and technological risks, and accelerate technology deployments. The NMFA represents the segment of EM that focuses on technological solutions for re-using, transforming, and disposing excess nuclear materials and is jointly managed by the DOE Albuquerque Operations Office and the DOE Idaho Operations Office.

  1. Undergraduate Nuclear Engineering Program Recognizing that in the US the nuclear industry is undergoing a renaissance and is hiring many engineers at one of the

    E-Print Network [OSTI]

    Virginia Tech

    Undergraduate Nuclear Engineering Program Background Recognizing that in the US the nuclear a world-class nuclear engineering education and research program. To satisfy the workforce needs program in nuclear engineering. We have connections with the DOE, Oak Ridge National Laboratory

  2. EIS-0203: Spent Nuclear Fuel Management and Idaho National Engineering Laboratory Environmental Restoration and Waste Management Programs

    Broader source: Energy.gov [DOE]

    Spent Nuclear Fuel Management and Idaho National Engineering Laboratory Environmental Restoration and Waste Management Programs

  3. National Nuclear Security Administration International Safeguards Education & Training Program(s)

    SciTech Connect (OSTI)

    Frazar, Sarah L.; McClelland-Kerr, John

    2009-10-06T23:59:59.000Z

    The introduction of nuclear power is a challenging, time-consuming and complex endeavor. After lengthy deliberations and research, some discover they are not prepared to take on the responsibilities or make the necessary investments to pursue nuclear power at this time. In particular, as countries begin to study their education systems with a critical eye, they discover they are unlikely to produce the requisite people to support the new plant they had hoped to introduce in the next ten to fifteen years. Without experienced personnel who can manage, operate, regulate and inspect the new plant, there is no point to building a plant in the first place. This paper will begin with an overview of various challenges associated with establishing and implementing a safe, secure and sustainable nuclear program and describe the some of the key issues that need to be addressed while planning to introduce nuclear power into an energy portfolio. Subsequent sections will describe how the United States is assisting countries in this planning process and in developing an effective workforce capable of supporting the nuclear program. Next, the paper will look at the key documents countries need to prepare in order to develop an effective workforce. The final section will offer some potential measures for success to ensure the long-term viability of the education system.

  4. Sandia starts silicon wafer production for three nuclear weapon programs |

    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 May Jun Jul(Summary)morphinanInformation Desert Southwest RegionatSearch WelcomeScienceProgramsSANDCurrentNational Nuclear Security

  5. The Meteorological Monitoring program at a former nuclear weapons plant

    SciTech Connect (OSTI)

    Maxwell, D.R.; Bowen, B.M.

    1994-02-01T23:59:59.000Z

    The purpose of the Meteorological Monitoring program at Rocky Flats Plant (RFP) is to provide meteorological information for use in assessing the transport, and diffusion, and deposition of effluent actually or potentially released into the atmosphere by plant operations. Achievement of this objective aids in protecting health and safety of the public, employees, and environment, and directly supports Emergency Response programs at RFP. Meteorological information supports the design of environmental monitoring networks for impact assessments, environmental surveillance activities, remediation activities, and emergency responses. As the mission of the plant changes from production of nuclear weapons parts to environmental cleanup and economic development, smaller releases resulting from remediation activities become more likely. These possible releases could result from airborne fugitive dust, evaporation from collection ponds, or grass fires.

  6. Next Generation Nuclear Plant Materials Research and Development Program Plan

    SciTech Connect (OSTI)

    G.O. Hayner; R.L. Bratton; R.N. Wright

    2005-09-01T23:59:59.000Z

    The U.S Department of Energy (DOE) has selected the Very High Temperature Reactor (VHTR) design for the Next Generation Nuclear Plant (NGNP) Project. The NGNP will demonstrate the use of nuclear power for electricity and hydrogen production without greenhouse gas emissions. The reactor design will be a graphite moderated, helium-cooled, prismatic or pebble-bed, thermal neutron spectrum reactor that will produce electricity and hydrogen in a state-of-the-art thermodynamically efficient manner. The NGNP will use very high burn-up, low-enriched uranium, TRISO-coated fuel and have a projected plant design service life of 60 years. The VHTR concept is considered to be the nearest-term reactor design that has the capability to efficiently produce hydrogen. The plant size, reactor thermal power, and core configuration will ensure passive decay heat removal without fuel damage or radioactive material releases during accidents. The NGNP Project is envisioned to demonstrate the following: (1) A full-scale prototype VHTR by about 2021; (2) High-temperature Brayton Cycle electric power production at full scale with a focus on economic performance; (3) Nuclear-assisted production of hydrogen (with about 10% of the heat) with a focus on economic performance; and (4) By test, the exceptional safety capabilities of the advanced gas-cooled reactors. Further, the NGNP program will: (1) Obtain a Nuclear Regulatory Commission (NRC) License to construct and operate the NGNP, this process will provide a basis for future performance based, risk-informed licensing; and (2) Support the development, testing, and prototyping of hydrogen infrastructures. The NGNP Materials Research and Development (R&D) Program is responsible for performing R&D on likely NGNP materials in support of the NGNP design, licensing, and construction activities. The NGNP Materials R&D Program includes the following elements: (1) Developing a specific approach, program plan and other project management tools for managing the R&D program elements; (2) Developing a specific work package for the R&D activities to be performed during each government fiscal year; (3) Reporting the status and progress of the work based on committed deliverables and milestones; (4) Developing collaboration in areas of materials R&D of benefit to the NGNP with countries that are a part of the Generation IV International Forum; and (5) Ensuring that the R&D work performed in support of the materials program is in conformance with established Quality Assurance and procurement requirements. The objective of the NGNP Materials R&D Program is to provide the essential materials R&D needed to support the design and licensing of the reactor and balance of plant, excluding the hydrogen plant. The materials R&D program is being initiated prior to the design effort to ensure that materials R&D activities are initiated early enough to support the design process and support the Project Integrator. The thermal, environmental, and service life conditions of the NGNP will make selection and qualification of some high-temperature materials a significant challenge; thus, new materials and approaches may be required.

  7. NEW - DOE O 452.1E, Nuclear Explosive and Weapon Surety Program

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

    All nuclear explosives and nuclear explosive operations require special safety, security, and use control consideration because of the potentially unacceptable consequences of an accident or unauthorized act; therefore, a Nuclear Explosive and Weapon Surety (NEWS) Program is established to prevent unintended/unauthorized detonation and deliberate unauthorized use of nuclear explosives.

  8. Technical and Political Assessment of Peaceful Nuclear Power Program Prospects in North Africa and the

    E-Print Network [OSTI]

    PNNL-16840 Technical and Political Assessment of Peaceful Nuclear Power Program Prospects in North and application of resources towards developing nuclear-generated electricity and nuclear-powered desalination nations have recently expressed interest in developing nuclear energy for peaceful purposes. Many

  9. DC, AC and advanced EV propulsion systems

    SciTech Connect (OSTI)

    O'Neil, W.

    1983-08-01T23:59:59.000Z

    Battery development and liquid fuel availability and cost are still the pacing factors in wide scale electric vehicle introduction. Propulsion systems also require technical development, however, if electric vehicles are to be acceptable in the marketplace in competition against ICE vehicles. Eaton Corporation has undertaken a program designed to identify and investigate three broad types of propulsion systems in identical test vehicles on the same test track under conditions as similar as possible. Characteristics of dc, ac and advanced systems are compared to date, and projections of anticipated results and further work are provided. The compelling advantages of multiple mechanical ratios in EV propulsion systems are reviewed. An emerging, but less obvious, advantage is higher overall system efficiency.

  10. Next Generation Nuclear Plant Research and Development Program Plan

    SciTech Connect (OSTI)

    None

    2005-01-01T23:59:59.000Z

    The U.S Department of Energy (DOE) is conducting research and development (R&D) on the Very High Temperature Reactor (VHTR) design concept for the Next Generation Nuclear Plant (NGNP) Project. The reactor design will be a graphite moderated, thermal neutron spectrum reactor that will produce electricity and hydrogen in a highly efficient manner. The NGNP reactor core could be either a prismatic graphite block type core or a pebble bed core. Use of a liquid salt coolant is also being evaluated. The NGNP will use very high-burnup, low-enriched uranium, TRISO-coated fuel, and have a projected plant design service life of 60 years. The VHTR concept is considered to be the nearest-term reactor design that has the capability to efficiently produce hydrogen. The plant size, reactor thermal power, and core configuration will ensure passive decay heat removal without fuel damage or radioactive material releases during accidents. The objectives of the NGNP Project are to: (1) Demonstrate a full-scale prototype VHTR that is commercially licensed by the U.S. Nuclear Regulatory Commission (2) Demonstrate safe and economical nuclear-assisted production of hydrogen and electricity. The DOE laboratories, led by the INL, will perform R&D that will be critical to the success of the NGNP, primarily in the areas of: (1) High temperature gas reactor fuels behavior; (2) High temperature materials qualification; (3) Design methods development and validation; (4) Hydrogen production technologies; and (5) Energy conversion. The current R&D work is addressing fundamental issues that are relevant to a variety of possible NGNP designs. This document describes the NGNP R&D planned and currently underway in the first three topic areas listed above. The NGNP Advanced Gas Reactor (AGR) Fuel Development and Qualification Program is presented in Section 2, the NGNP Materials R&D Program Plan is presented in Section 3, and the NGNP Design Methods Development and Validation R&D Program is presented in Section 4. The DOE-funded hydrogen production [DOE 2004] and energy conversion technologies programs are described elsewhere.

  11. Management of National Nuclear Power Programs for assured safety

    SciTech Connect (OSTI)

    Connolly, T.J. (ed.)

    1985-01-01T23:59:59.000Z

    Topics discussed in this report include: nuclear utility organization; before the Florida Public Service Commission in re: St. Lucie Unit No. 2 cost recovery; nuclear reliability improvement and safety operations; nuclear utility management; training of nuclear facility personnel; US experience in key areas of nuclear safety; the US Nuclear Regulatory Commission - function and process; regulatory considerations of the risk of nuclear power plants; overview of the processes of reliability and risk management; management significance of risk analysis; international and domestic institutional issues for peaceful nuclear uses; the role of the Institute of Nuclear Power Operations (INPO); and nuclear safety activities of the International Atomic Energy Agency (IAEA).

  12. Self-Reliability and Motivation in a Nuclear Security Culture Enhancement Program

    SciTech Connect (OSTI)

    Crawford,C.; de Boer,G.; De Castro, K; Landers, Ph.D., J; Rogers, E

    2009-10-19T23:59:59.000Z

    The threat of nuclear terrorism has become a global concern. Many countries continue to make efforts to strengthen nuclear security by enhancing systems of nuclear material protection, control, and accounting (MPC&A). Though MPC&A systems can significantly upgrade nuclear security, they do not eliminate the "human factor." This paper will describe some of the key elements of a comprehensive, sustainable nuclear security culture enhancement program and how implementation can mitigate the insider threat.

  13. Next Generation Nuclear Plant Methods Technical Program Plan

    SciTech Connect (OSTI)

    Richard R. Schultz; Abderrafi M. Ougouag; David W. Nigg; Hans D. Gougar; Richard W. Johnson; William K. Terry; Chang H. Oh; Donald W. McEligot; Gary W. Johnsen; Glenn E. McCreery; Woo Y. Yoon; James W. Sterbentz; J. Steve Herring; Temitope A. Taiwo; Thomas Y. C. Wei; William D. Pointer; Won S. Yang; Michael T. Farmer; Hussein S. Khalil; Madeline A. Feltus

    2007-01-01T23:59:59.000Z

    One of the great challenges of designing and licensing the Very High Temperature Reactor (VHTR) is to confirm that the intended VHTR analysis tools can be used confidently to make decisions and to assure all that the reactor systems are safe and meet the performance objectives of the Generation IV Program. The research and development (R&D) projects defined in the Next Generation Nuclear Plant (NGNP) Design Methods Development and Validation Program will ensure that the tools used to perform the required calculations and analyses can be trusted. The Methods R&D tasks are designed to ensure that the calculational envelope of the tools used to analyze the VHTR reactor systems encompasses, or is larger than, the operational and transient envelope of the VHTR itself. The Methods R&D focuses on the development of tools to assess the neutronic and thermal fluid behavior of the plant. The fuel behavior and fission product transport models are discussed in the Advanced Gas Reactor (AGR) program plan. Various stress analysis and mechanical design tools will also need to be developed and validated and will ultimately also be included in the Methods R&D Program Plan. The calculational envelope of the neutronics and thermal-fluids software tools intended to be used on the NGNP is defined by the scenarios and phenomena that these tools can calculate with confidence. The software tools can only be used confidently when the results they produce have been shown to be in reasonable agreement with first-principle results, thought-problems, and data that describe the highly ranked phenomena inherent in all operational conditions and important accident scenarios for the VHTR.

  14. Next Generation Nuclear Plant Methods Technical Program Plan

    SciTech Connect (OSTI)

    Richard R. Schultz; Abderrafi M. Ougouag; David W. Nigg; Hans D. Gougar; Richard W. Johnson; William K. Terry; Chang H. Oh; Donald W. McEligot; Gary W. Johnsen; Glenn E. McCreery; Woo Y. Yoon; James W. Sterbentz; J. Steve Herring; Temitope A. Taiwo; Thomas Y. C. Wei; William D. Pointer; Won S. Yang; Michael T. Farmer; Hussein S. Khalil; Madeline A. Feltus

    2010-12-01T23:59:59.000Z

    One of the great challenges of designing and licensing the Very High Temperature Reactor (VHTR) is to confirm that the intended VHTR analysis tools can be used confidently to make decisions and to assure all that the reactor systems are safe and meet the performance objectives of the Generation IV Program. The research and development (R&D) projects defined in the Next Generation Nuclear Plant (NGNP) Design Methods Development and Validation Program will ensure that the tools used to perform the required calculations and analyses can be trusted. The Methods R&D tasks are designed to ensure that the calculational envelope of the tools used to analyze the VHTR reactor systems encompasses, or is larger than, the operational and transient envelope of the VHTR itself. The Methods R&D focuses on the development of tools to assess the neutronic and thermal fluid behavior of the plant. The fuel behavior and fission product transport models are discussed in the Advanced Gas Reactor (AGR) program plan. Various stress analysis and mechanical design tools will also need to be developed and validated and will ultimately also be included in the Methods R&D Program Plan. The calculational envelope of the neutronics and thermal-fluids software tools intended to be used on the NGNP is defined by the scenarios and phenomena that these tools can calculate with confidence. The software tools can only be used confidently when the results they produce have been shown to be in reasonable agreement with first-principle results, thought-problems, and data that describe the highly ranked phenomena inherent in all operational conditions and important accident scenarios for the VHTR.

  15. Next Generation Nuclear Plant Methods Technical Program Plan -- PLN-2498

    SciTech Connect (OSTI)

    Richard R. Schultz; Abderrafi M. Ougouag; David W. Nigg; Hans D. Gougar; Richard W. Johnson; William K. Terry; Chang H. Oh; Donald W. McEligot; Gary W. Johnsen; Glenn E. McCreery; Woo Y. Yoon; James W. Sterbentz; J. Steve Herring; Temitope A. Taiwo; Thomas Y. C. Wei; William D. Pointer; Won S. Yang; Michael T. Farmer; Hussein S. Khalil; Madeline A. Feltus

    2010-09-01T23:59:59.000Z

    One of the great challenges of designing and licensing the Very High Temperature Reactor (VHTR) is to confirm that the intended VHTR analysis tools can be used confidently to make decisions and to assure all that the reactor systems are safe and meet the performance objectives of the Generation IV Program. The research and development (R&D) projects defined in the Next Generation Nuclear Plant (NGNP) Design Methods Development and Validation Program will ensure that the tools used to perform the required calculations and analyses can be trusted. The Methods R&D tasks are designed to ensure that the calculational envelope of the tools used to analyze the VHTR reactor systems encompasses, or is larger than, the operational and transient envelope of the VHTR itself. The Methods R&D focuses on the development of tools to assess the neutronic and thermal fluid behavior of the plant. The fuel behavior and fission product transport models are discussed in the Advanced Gas Reactor (AGR) program plan. Various stress analysis and mechanical design tools will also need to be developed and validated and will ultimately also be included in the Methods R&D Program Plan. The calculational envelope of the neutronics and thermal-fluids software tools intended to be used on the NGNP is defined by the scenarios and phenomena that these tools can calculate with confidence. The software tools can only be used confidently when the results they produce have been shown to be in reasonable agreement with first-principle results, thought-problems, and data that describe the highly ranked phenomena inherent in all operational conditions and important accident scenarios for the VHTR.

  16. Next Generation Nuclear Plant Research and Development Program Plan

    SciTech Connect (OSTI)

    P. E. MacDonald

    2005-01-01T23:59:59.000Z

    The U.S Department of Energy (DOE) is conducting research and development (R&D) on the Very High Temperature Reactor (VHTR) design concept for the Next Generation Nuclear Plant (NGNP) Project. The reactor design will be a graphite moderated, thermal neutron spectrum reactor that will produce electricity and hydrogen in a highly efficient manner. The NGNP reactor core could be either a prismatic graphite block type core or a pebble bed core. Use of a liquid salt coolant is also being evaluated. The NGNP will use very high-burnup, low-enriched uranium, TRISO-coated fuel, and have a projected plant design service life of 60 years. The VHTR concept is considered to be the nearest-term reactor design that has the capability to efficiently produce hydrogen. The plant size, reactor thermal power, and core configuration will ensure passive decay heat removal without fuel damage or radioactive material releases during accidents. The objectives of the NGNP Project are to: Demonstrate a full-scale prototype VHTR that is commercially licensed by the U.S. Nuclear Regulatory Commission Demonstrate safe and economical nuclearassisted production of hydrogen and electricity. The DOE laboratories, led by the INL, will perform R&D that will be critical to the success of the NGNP, primarily in the areas of: High temperature gas reactor fuels behavior High temperature materials qualification Design methods development and validation Hydrogen production technologies Energy conversion. The current R&D work is addressing fundamental issues that are relevant to a variety of possible NGNP designs. This document describes the NGNP R&D planned and currently underway in the first three topic areas listed above. The NGNP Advanced Gas Reactor (AGR) Fuel Development and Qualification Program is presented in Section 2, the NGNP Materials R&D Program Plan is presented in Section 3, and the NGNP Design Methods Development and Validation R&D Program is presented in Section 4. The DOE-funded hydrogen production [DOE 2004] and energy conversion technologies programs are described elsewhere.

  17. The Soviet program for peaceful uses of nuclear explosions

    SciTech Connect (OSTI)

    Nordyke, M.D.

    1996-07-24T23:59:59.000Z

    The concept of utilizing the weapons of war to serve the peaceful pursuits of mankind is as old as civilization itself. Perhaps the most famous reference to this basic desire is recorded in the Book of Micah where the great prophet Isiah called upon his people `to turn your spears into pitchforks and your swords into plowshares.` As the scientists at Los Alamos worked on developing the world`s first atomic bomb, thoughts of how this tremendous new source of energy could be used for peaceful purposes generally focused on using the thermal energy generated by the slow fission of uranium in a reactor, such as those being used to produce Plutonium to drive electric power stations. However, being scientists in a new, exciting field, it was impossible to avoid letting their minds wander from the task at hand to other scientific or non-military uses for the bombs themselves. During the Manhattan Project, Otto Frisch, one of the pioneers in the development of nuclear fission process in the 1930s, first suggested using an atomic explosion as a source for a large quantities of neutrons which could used in scientific experiments designed to expand their understanding of nuclear physics. After the war was over, many grandiose ideas appeared in the popular press on how this new source of energy should be to serve mankind. Not to be left out of the growing enthusiasm for peaceful uses of atomic energy, the Soviet Union added their visions to the public record. This document details the Soviet program for using nuclear explosions in peacetime pursuits.

  18. Nuclear Engineering & Radiation Health Physics Program Outcomes Ability to apply knowledge of mathematics, science, and engineering

    E-Print Network [OSTI]

    Tullos, Desiree

    Nuclear Engineering & Radiation Health Physics Program Outcomes · Ability to apply knowledge for engineering practice · Ability to apply knowledge of atomic and nuclear physics to nuclear and radiological of mathematics, science, and engineering · Ability to design and conduct experiments as well as analyze

  19. Design, Analysis, and Simulation of Rocket Propulsion System

    E-Print Network [OSTI]

    Kulhanek, Sarah Logan

    2012-08-31T23:59:59.000Z

    . The program currently provides a symbolic link in the form of a button on the output page which will open Unigraphics NX CAD program. The post-processing simulation of the rocket propulsion system is done in a computational fluid dynamics (CFD) program...

  20. High Energy Density Laboratory Plasmas Program | National Nuclear...

    National Nuclear Security Administration (NNSA)

    Photo Gallery Jobs Apply for Our Jobs Our Jobs Working at NNSA Blog Home High Energy Density Laboratory Plasmas Program High Energy Density Laboratory Plasmas Program...

  1. Small Business Teaming Workshop Program | National Nuclear Security...

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

    Photo Gallery Jobs Apply for Our Jobs Our Jobs Working at NNSA Blog Home Small Business Teaming Workshop Program Small Business Teaming Workshop Program To increase small...

  2. Program Management at the National Nuclear Security Administration Office of Defense Nuclear Security: A Review of Program Management Documents and Underlying Processes

    SciTech Connect (OSTI)

    Madden, Michael S.

    2010-05-01T23:59:59.000Z

    The scope of this paper is to review the National Nuclear Security Administration Office of Defense Nuclear Security (DNS) program management documents and to examine the underlying processes. The purpose is to identify recommendations for improvement and to influence the rewrite of the DNS Program Management Plan (PMP) and the documentation supporting it. As a part of this process, over 40 documents required by DNS or its stakeholders were reviewed. In addition, approximately 12 other documents produced outside of DNS and its stakeholders were reviewed in an effort to identify best practices. The complete list of documents reviewed is provided as an attachment to this paper.

  3. A program in Medium-Energy Nuclear Physics

    SciTech Connect (OSTI)

    Berman, B.L.

    1991-12-31T23:59:59.000Z

    This report discusses research on the following topics: single electron scattering; coincidence electron scattering; photonuclear reactions; pion scattering; and the GWU nuclear detector. (LSP).

  4. A program in Medium-Energy Nuclear Physics

    SciTech Connect (OSTI)

    Berman, B.L.

    1991-01-01T23:59:59.000Z

    This report discusses research on the following topics: single electron scattering; coincidence electron scattering; photonuclear reactions; pion scattering; and the GWU nuclear detector. (LSP).

  5. Order Module--DOE O 433.1B, MAINTENANCE MANAGEMENT PROGRAM FOR DOE NUCLEAR FACILITIES

    Broader source: Energy.gov [DOE]

    "The familiar level of this module is designed to summarize the basic information in DOE O 433.1B, Maintenance Management Program for DOE Nuclear Facilities. This Order canceled DOE O 433.1A. This...

  6. Nuclear Facility Maintenance Management Program Guide for Use with DOE O 433.1B

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

    2011-09-12T23:59:59.000Z

    The guide provides acceptable approaches for implementing requirements for Nuclear Maintenance Management Programs (NMMPs) set forth in DOE O 433.1B. Cancels DOE G 433.1-1.

  7. Senior Technical Safety Manager Qualification Program Self-Assessment- Chief of Nuclear Safety

    Broader source: Energy.gov [DOE]

    This Chief of Nuclear Safety (CNS) Report was prepared to summarize the results of the July 2013 CNS self-assessment of the Senior Technical Safety Manager Qualification Program.

  8. Life Cycle Modeling of Propulsion Materials

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

    propulsion materials manufacturing technologies with an emphasis on aluminum, magnesium, titanium, and ceramics * Advanced propulsion materials' potential in heavy-duty...

  9. Nuclear criticality safety program at the University of Tennessee-Knoxville

    SciTech Connect (OSTI)

    Basoglu, B.; Bentley, C.; Brewer, R.; Dunn, M.; Haught, C.; Plaster, M.; Wilkinson, A.; Dodds, H. (Univ. of Tennessee, Knoxville, TN (United States)); Elliott, E.; Waddell, W. (Martin Marietta Energy Systems Inc., Oak Ridge, TN (United States))

    1993-01-01T23:59:59.000Z

    This paper presents an overview of the nuclear criticality safety (NCS) educational program at the University of Tennessee-Knoxville. The program is an academic specialization for nuclear engineering graduate students pursuing either the MS or PhD degree and includes special NCS courses and NCS research projects. Both the courses and the research projects serve as partial fulfillment of the requirements for the degree being pursued.

  10. Implementation Plan for the Office of Nuclear Energy Knowledge Management Program

    SciTech Connect (OSTI)

    Kimberlyn C. Mousseau

    2011-12-01T23:59:59.000Z

    The primary purpose of the Department of Energy (DOE), Office of Nuclear Energy (NE) Knowledge Management (KM) Program is to capture, share, disseminate, and ensure the ability to apply the knowledge created by the major nuclear energy Research and Development (R&D) programs. In support of the KM program, the Implementation Plan for the Office of NE KM Program outlines the knowledge management and distributed data environment that is required for its success. In addition to enumerating some strategic goals and objectives, this document characterizes the initial program and identifies computer-based areas of investment required for increased knowledge sharing and collaboration. It identifies and addresses investments already in existence and describes how these investments can be further enhanced and implemented to support a distributed KM program. The Idaho National Laboratory (INL) is leading the effort to identify and address these investments through the implementation of a distributed KM program that includes participants from ten of the major DOE national laboratories.

  11. Self-imposed self-assessment program at a DOE Nuclear Facility

    SciTech Connect (OSTI)

    Geoffrion, R.R.; Loud, J.J.; Walter, E.C. [Los Alamos National Laboratory, NM (United States)

    1996-12-31T23:59:59.000Z

    The Nuclear Materials and Technology (NMT) Division at Los Alamos National Laboratory (LANL) has implemented a performance-based self-assessment program at the TA-55 plutonium facility. The program was conceptualized and developed by LANL`s internal assessment group, AA-2. The management walkaround program fosters continuous improvement in NMT products and performance of its activities. The program, based on experience from the Institute of Nuclear Power Operations, is endorsed at the site by the U.S. Department of Energy (DOE) Environment, Safety, and Health (ES&H) personnel and by the Defense Nuclear Facility Safety Board. The self-assessment program focuses on how work is actually performed rather than on paperwork or process compliance. Managers critically and continually assess ES&H, conduct of operations, and other functional area requirements.

  12. Second Line of Defense Program | National Nuclear Security Administrat...

    National Nuclear Security Administration (NNSA)

    airports and seaports, internal country locations, and maritime borders. Sustainability Program: providing guidance, methodology, and practical transition support for the...

  13. The Need for a Strong Science and Technology Program in the Nuclear Weapons Complex for the 21st Century

    SciTech Connect (OSTI)

    Garaizar, X

    2010-01-06T23:59:59.000Z

    In this paper I argue for the need for a strong Science and Technology program in the Nuclear Weapons Complex as the basis for maintaining a credible deterrence capability. The current Nuclear Posture Review establishes a New Triad as the basis for the United States deterrence strategy in a changing security environment. A predictive science capability is at the core of a credible National Nuclear Weapons program in the 21st Century. In absence of nuclear testing, the certification of our current Nuclear Weapons relies on predictive simulations and quantification of the associated simulation uncertainties. In addition, a robust nuclear infrastructure needs an active research and development program that considers all the required nuclear scenarios, including new configurations for which there is no nuclear test data. This paper also considers alternative positions to the need for a Science and Technology program in the Nuclear Weapons complex.

  14. Military Academy Cadet/Midshipman Program | National Nuclear...

    National Nuclear Security Administration (NNSA)

    point of contact will coordinate with NNSA to work out the details between you, your school and the site you've selected. If you're not sure where you might fit into the nuclear...

  15. A program in medium-energy nuclear physics

    SciTech Connect (OSTI)

    Berman, B.L.; Dhuga, K.S.

    1990-01-01T23:59:59.000Z

    This report discusses the following topics: electron-scattering nuclear-structure studies; coincidence electrodisintegration studies of light nuclei; pion scattering and reactions on the three-body nuclei; and pion scattering from shell-model nuclei.

  16. Russia-U.S. joint program on the safe management of nuclear materials

    SciTech Connect (OSTI)

    Witmer, F.E.; Krumpe, P.F. [Dept. of Energy, Washington, DC (United States); Carlson, D.D. [Sandia National Labs., Albuquerque, NM (United States)] [and others

    1998-06-01T23:59:59.000Z

    The Russia-US joint program on the safe management of nuclear materials was initiated to address common technical issues confronting the US and Russia in the management of excess weapons grade nuclear materials. The program was initiated after the 1993 Tomsk-7 accident. This paper provides an update on program activities since 1996. The Fourth US Russia Nuclear Materials Safety Management Workshop was conducted in March 1997. In addition, a number of contracts with Russian Institutes have been placed by Lawrence Livermore National Laboratory (LLNL) and Sandia National Laboratories (SNL). These contracts support research related to the safe disposition of excess plutonium (Pu) and highly enriched uranium (HEU). Topics investigated by Russian scientists under contracts with SNL and LLNL include accident consequence studies, the safety of anion exchange processes, underground isolation of nuclear materials, and the development of materials for the immobilization of excess weapons Pu.

  17. Systems engineering programs for geologic nuclear waste disposal

    SciTech Connect (OSTI)

    Klett, R. D.; Hertel, Jr., E. S.; Ellis, M. A.

    1980-06-01T23:59:59.000Z

    The design sequence and system programs presented begin with general approximate solutions that permit inexpensive analysis of a multitude of possible wastes, disposal media, and disposal process properties and configurations. It then continues through progressively more precise solutions as parts of the design become fixed, and ends with repository and waste form optimization studies. The programs cover both solid and gaseous waste forms. The analytical development, a program listing, a users guide, and examples are presented for each program. Sensitivity studies showing the effects of disposal media and waste form thermophysical properties and repository layouts are presented as examples.

  18. Uranium from Seawater Program Review; Fuel Resources Uranium from Seawater Program DOE Office of Nuclear Energy

    SciTech Connect (OSTI)

    none,

    2013-07-01T23:59:59.000Z

    For nuclear energy to remain sustainable in the United States, economically viable sources of uranium beyond terrestrial ores must be developed. The goal of this program is to develop advanced adsorbents that can extract uranium from seawater at twice the capacity of the best adsorbent developed by researchers at the Japan Atomic Energy Agency (JAEA), 1.5 mg U/g adsorbent. A multidisciplinary team from Oak Ridge National Laboratory, Lawrence Berkeley National Laboratory, Pacific Northwest National Laboratory, and the University of Texas at Austin was assembled to address this challenging problem. Polymeric adsorbents, based on the radiation grafting of acrylonitrile and methacrylic acid onto high surface-area polyethylene fibers followed by conversion of the nitriles to amidoximes, have been developed. These poly(acrylamidoxime-co-methacrylic acid) fibers showed uranium adsorption capacities for the extraction of uranium from seawater that exceed 3 mg U/g adsorbent in testing at the Pacific Northwest National Laboratory Marine Sciences Laboratory. The essence of this novel technology lies in the unique high surface-area trunk material that considerably increases the grafting yield of functional groups without compromising its mechanical properties. This technology received an R&D100 Award in 2012. In addition, high surface area nanomaterial adsorbents are under development with the goal of increasing uranium adsorption capacity by taking advantage of the high surface areas and tunable porosity of carbon-based nanomaterials. Simultaneously, de novo structure-based computational design methods are being used to design more selective and stable ligands and the most promising candidates are being synthesized, tested and evaluated for incorporation onto a support matrix. Fundamental thermodynamic and kinetic studies are being carried out to improve the adsorption efficiency, the selectivity of uranium over other metals, and the stability of the adsorbents. Understanding the rate-limiting step of uranium uptake from seawater is also essential in designing an effective uranium recovery system. Finally, economic analyses have been used to guide these studies and highlight what parameters, such as capacity, recyclability, and stability, have the largest impact on the cost of extraction of uranium from seawater. Initially, the cost estimates by the JAEA for extraction of uranium from seawater with braided polymeric fibers functionalized with amidoxime ligands were evaluated and updated. The economic analyses were subsequently updated to reflect the results of this project while providing insight for cost reductions in the adsorbent development through cradle-to-grave case studies for the extraction process. This report highlights the progress made over the last three years on the design, synthesis, and testing of new materials to extract uranium for seawater. This report is organized into sections that highlight the major research activities in this project: (1) Chelate Design and Modeling, (2) Thermodynamics, Kinetics and Structure, (3) Advanced Polymeric Adsorbents by Radiation Induced Grafting, (4) Advanced Nanomaterial Adsorbents, (5) Adsorbent Screening and Modeling, (6) Marine Testing, and (7) Cost and Energy Assessment. At the end of each section, future research directions are briefly discussed to highlight the challenges that still remain to reduce the cost of extractions of uranium for seawater. Finally, contributions from the Nuclear Energy University Programs (NEUP), which complement this research program, are included at the end of this report.

  19. Next Generation Nuclear Plant Materials Selection and Qualification Program Plan

    SciTech Connect (OSTI)

    R. Doug Hamelin; G. O. Hayner

    2004-11-01T23:59:59.000Z

    The U.S. Department of Energy (DOE) has selected the Very High Temperature Reactor (VHTR) design for the Next Generation Nuclear Plant (NGNP) Project. The NGNP will demonstrate the use of nuclear power for electricity and hydrogen production without greenhouse gas emissions. The reactor design is a graphite-moderated, helium-cooled, prismatic or pebble bed thermal neutron spectrum reactor with an average reactor outlet temperature of at least 1000 C. The NGNP will use very high burn up, lowenriched uranium, TRISO-Coated fuel in a once-through fuel cycle. The design service life of the NGNP is 60 years.

  20. Next Generation Nuclear Plant Materials Research and Development Program Plan

    SciTech Connect (OSTI)

    G. O. Hayner; E.L. Shaber

    2004-09-01T23:59:59.000Z

    The U.S Department of Energy (DOE) has selected the Very High Temperature Reactor (VHTR) design for the Next Generation Nuclear Plant (NGNP) Project. The NGNP will demonstrate the use of nuclear power for electricity and hydrogen production without greenhouse gas emissions. The reactor design will be a graphite moderated, helium-cooled, prismatic or pebble-bed, thermal neutron spectrum reactor that will produce electricity and hydrogen in a state-of-the-art thermodynamically efficient manner. The NGNP will use very high burn-up, low-enriched uranium, TRISO-coated fuel and have a projected plant design service life of 60 years.

  1. Sandia National Laboratories: Nuclear Energy and Fuel Cycle Programs

    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 Administration the1 -theErik Spoerke SSLSMolten-Salt StorageNo More GreenWorkshops Nuclear

  2. Judgment and Decision Making, Vol. 4, No. 7, December 2009, pp. 930933 Emerging sacred values: Iran's nuclear program

    E-Print Network [OSTI]

    Paris-Sud XI, Université de

    : Iran's nuclear program Morteza Dehghani1 , Rumen Iliev1 , Sonya Sachdeva1 , Scott Atran2 , Jeremy values, negotiation, Iran, nuclear ambitions, sanctions 1 Introduction At least since the end

  3. Strategic Technology JET PROPULSION LABORATORY

    E-Print Network [OSTI]

    Waliser, Duane E.

    Strategic Technology Directions JET PROPULSION LABORATORY National Aeronautics and Space Administration 2 0 0 9 #12;© 2009 California Institute of Technology. Government sponsorship acknowledged. #12;Strategic Technology Directions 2009 offers a distillation of technologies, their links to space missions

  4. Space nuclear safety program. Progress report, July 1983

    SciTech Connect (OSTI)

    Bronisz, S.E. (comp.)

    1983-11-01T23:59:59.000Z

    This technical monthly report covers studies related to the use of /sup 238/PuO/sub 2/ in radioisotope power systems carried out for the Office of Special Nuclear Projects of the US Department of Energy by Los Alamos National Laboratory. Most of the studies discussed here are ongoing. Results and conclusions described may change as the work continues.

  5. The U.S. national nuclear forensics library, nuclear materials information program, and data dictionary

    SciTech Connect (OSTI)

    Lamont, Stephen Philip [Los Alamos National Laboratory; Brisson, Marcia [DOE-IN; Curry, Michael [DEPT. OF STATE

    2011-02-17T23:59:59.000Z

    Nuclear forensics assessments to determine material process history requires careful comparison of sample data to both measured and modeled nuclear material characteristics. Developing centralized databases, or nuclear forensics libraries, to house this information is an important step to ensure all relevant data will be available for comparison during a nuclear forensics analysis and help expedite the assessment of material history. The approach most widely accepted by the international community at this time is the implementation of National Nuclear Forensics libraries, which would be developed and maintained by individual nations. This is an attractive alternative toan international database since it provides an understanding that each country has data on materials produced and stored within their borders, but eliminates the need to reveal any proprietary or sensitive information to other nations. To support the concept of National Nuclear Forensics libraries, the United States Department of Energy has developed a model library, based on a data dictionary, or set of parameters designed to capture all nuclear forensic relevant information about a nuclear material. Specifically, information includes material identification, collection background and current location, analytical laboratories where measurements were made, material packaging and container descriptions, physical characteristics including mass and dimensions, chemical and isotopic characteristics, particle morphology or metallurgical properties, process history including facilities, and measurement quality assurance information. While not necessarily required, it may also be valuable to store modeled data sets including reactor burn-up or enrichment cascade data for comparison. It is fully expected that only a subset of this information is available or relevant to many materials, and much of the data populating a National Nuclear Forensics library would be process analytical or material accountability measurement data as opposed to a complete forensic analysis of each material in the library.

  6. Implications of a North Korean Nuclear Weapons Program

    SciTech Connect (OSTI)

    Lehman, R.F. II

    1993-07-01T23:59:59.000Z

    The Democratic People`s Republic of Korea (DPRK) is one of the Cold War`s last remaining totalitarian regimes. Rarely has any society been as closed to outside influences and so distant from political, economic, and military developments around the globe. In 1991 and in 1992, however, this dictatorship took a number of political steps which increased Pyongyang`s interaction with the outside world. Although North Korea`s style of engagement with the broader international community involved frequent pauses and numerous steps backward, many observers believed that North Korea was finally moving to end its isolated, outlaw status. As the end of 1992 approached, however, delay and obstruction by Pyongyang became intense as accumulating evidence suggested that the DPRK, in violation of the nuclear Non-Proliferation Treaty (NPT), was seeking to develop nuclear weapons. On March 12, 1993, North Korea announced that it would not accept additional inspections proposed by the International Atomic Energy Agency (IAEA) to resolve concerns about possible violations and instead would withdraw from the Treaty. Pyongyang`s action raised the specter that, instead of a last act of the Cold War, North Korea`s diplomatic maneuvering would unravel the international norms that were to be the basis of stability and peace in the post-Cold War era. Indeed, the discovery that North Korea was approaching the capability to produce nuclear weapons suggested that the nuclear threat, which had been successfully managed throughout the Cold War era, could increase in the post-Cold War era.

  7. NNSA employees selected for Nuclear Scholars Initiative program | National

    National Nuclear Security Administration (NNSA)

    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) "ofEarlyEnergyDepartmentNational Nuclear

  8. Evaluating Russian space nuclear reactor technology for United States applications

    SciTech Connect (OSTI)

    Polansky, G.F. [Phillips Lab., Albuquerque, NM (United States); Schmidt, G.L. [New Mexico Engineering Research Institute, Albuquerque, NM (United States); Voss, S.S. [Los Alamos National Lab., NM (United States); Reynolds, E.L. [Applied Physics Lab., Laurel, MD (United States)

    1994-08-01T23:59:59.000Z

    Space nuclear power and nuclear electric propulsion are considered important technologies for planetary exploration, as well as selected earth orbit applications. The Nuclear Electric Propulsion Space Test Program (NEPSTP) was intended to provide an early flight demonstration of these technologies at relatively low cost through extensive use of existing Russian technology. The key element of Russian technology employed in the program was the Topaz II reactor. Refocusing of the activities of the Ballistic Missile Defense Organization (BMDO), combined with budgetary pressures, forced the cancellation of the NEPSTP at the end of the 1993 fiscal year. The NEPSTP was faced with many unique flight qualification issues. In general, the launch of a spacecraft employing a nuclear reactor power system complicates many spacecraft qualification activities. However, the NEPSTP activities were further complicated because the reactor power system was a Russian design. Therefore, this program considered not only the unique flight qualification issues associated with space nuclear power, but also with differences between Russian and United States flight qualification procedures. This paper presents an overview of the NEPSTP. The program goals, the proposed mission, the spacecraft, and the Topaz II space nuclear power system are described. The subject of flight qualification is examined and the inherent difficulties of qualifying a space reactor are described. The differences between United States and Russian flight qualification procedures are explored. A plan is then described that was developed to determine an appropriate flight qualification program for the Topaz II reactor to support a possible NEPSTP launch.

  9. A Program to Stabilize Nuclear Materials as Managed by the Plutonium Focus Area

    SciTech Connect (OSTI)

    B. Kenley (Kenley Consulting); B. Scott; B. Seidel (ANL-W); D. Knecht (LMITCO); F. Southworth; K. Osborne (DOE-ID); N. Chipman; T. Creque

    1999-03-01T23:59:59.000Z

    This paper describes the program to stabilize nuclear materials, consistent with the Department of Energy Office of Environmental Management (EM) plan, Accelerating Cleanup: Paths to Closure. The program is managed by the Plutonium Stabilization and Disposition Focus Area, which defines and manages technology development programs to stabilize nuclear materials and assure their subsequent safe storage and final disposition. The scope of the Plutonium Stabilization and Disposition Focus Area (PFA) activities includes non-weapons plutonium materials, special isotopes, and other fissile materials. The PFA provides solutions to site-specific and complex wide technology issues associated with plutonium remediation, stabilization, and preparation for disposition. Our paper describes an important programmatic function of the Department of Energy nuclear materials stabilization program, including the tie-in of policy to research needs and funding for the nuclear materials disposition area. The PFA uses a rigorous systems engineering determination of technology needs and gaps, under the guidance of a Technical Advisory Panel, consisting of complex-wide experts. The Research and Development planning provides an example for other waste areas and should be of interest to Research and Development managers. The materials disposition maps developed by the PFA and described in this paper provide an evaluation of research needs, data gaps and subsequent guidance for the development of technologies for nuclear materials disposition. This paper also addresses the PFA prioritization methodology and its ability to forecast actual time to implementation.

  10. Topics in nuclear and radiochemistry for college curricula and high school science programs

    SciTech Connect (OSTI)

    Not Available

    1990-01-01T23:59:59.000Z

    The concern with the current status and trends of nuclear chemistry and radiochemistry education in academic institutions was addressed in a recent workshop. The 1988 workshop considered the important contributions that scientist with nuclear and radiochemistry backgrounds have made and are continuing to make to other sciences and to various applied fields. Among the areas discussed were environmental studies, life sciences, materials science, separation technology, hot atom chemistry, cosmochemistry, and the rapidly growing field of nuclear medicine. It is intent of the organizer and participants of this symposium entitled Topics in Nuclear and Radiochemistry for College Curricula and High School Science Program'' to provide lecture material on topics related to nuclear and radiochemistry to educators. It is our hope that teachers, who may or may not be familiar with the field, will find this collections of articles useful and incorporate some of them into their lectures.

  11. UPDATE: nuclear power program information and data, July-September 1981

    SciTech Connect (OSTI)

    DOE /NBM--6011986

    1981-01-01T23:59:59.000Z

    UPDATE is published by the Office of Coordination and Special Projects, Office of Nuclear Reactor Programs, to provide a quick reference source on the current status of nuclear powerplant construction and operation in the United States and for information on the fuel cycle, economics, and performance of nuclear generating units. Similar information on other means of electric generation as related to nuclear power is included when appropriate. The subject matter of the reports and analyses presented in UPDATE will vary from issue to issue, reflecting changes in foci of interest and new developments in the field of commercial nuclear power generation. UPDATA is intended to provide a timely source of current statistics, results of analyses, and programmatic information proceeding from the activities of the Office of Nuclear Reactor Programs and other components of the Department of Energy, as well as condensations of topical articles from other sources of interest to the nuclear community. It also facilitates quick responses to requests for data and information of the type often solicited from this office.

  12. Update: nuclear power program information and data, March-April 1981

    SciTech Connect (OSTI)

    Not Available

    1981-01-01T23:59:59.000Z

    UPDATE is published by the Office of Coordination and Special Projects, Office of Nuclear Reactor Programs, to provide a quick reference source on the current status of nuclear powerplant construction and operation in the United States and for information on the fuel cycle, economics, and performance of nuclear generating units. Similar information on other means of electric generation as related to nuclear power is included when appropriate. The subject matter of the reports and analyses presented in UPDATE will vary from issue to issue, reflecting changes in foci of interest and new developments in the field of commercial nuclear power generation. UPDATE is intended to provide a timely source of current statistics, results of analyses, and programmatic information proceeding from the activities of the Office of Nuclear Reactor Programs and other components of the Department of Energy, as well as condensations of topical articles from other sources of interest to the nuclear community. It also facilitates quick responses to requests for data and information of the type often solicited from this office.

  13. Update: nuclear power program information and data, October-December 1981

    SciTech Connect (OSTI)

    Not Available

    1981-01-01T23:59:59.000Z

    UPDATE is published by the Office of Coordination and Special Projects, Office of Nuclear Reactor Programs, to provide a quick reference source on the current status of nuclear powerplant construction and operation in the United States and for information on the fuel cycle, economics, and performance of nuclear generating units. Similar information on other means of electric generation as related to nuclear power is included when appropriate. The subject matter of the reports and analyses presented in UPDATE will vary from issue to issue, reflecting changes in foci of interest and new developments in the field of commercial nuclear power generation. UPDATE is intended to provide a timely source of current statistics, results of analyses, and programmatic information proceeding from the activities of the Office of Nuclear Reactor Programs and other components of the Department of Energy, as well as condensations of topical articles from other sources of interest to the nuclear community. It also facilitates quick responses to requests for data and information of the type often solicited from this office.

  14. Russian-U.S. joint program on the safe management of nuclear materials

    SciTech Connect (OSTI)

    Witmer, F.E.; Krumpe, P.F. [Dept. of Energy, Washington, DC (US); Carlson, D.D. [Sandia National Labs., Albuquerque, NM (US)] [and others

    1997-12-01T23:59:59.000Z

    The Russian-US joint program on the safety of nuclear materials was initiated in response to the 1993 Tomsk-7 accident. The bases for this program are the common technical issues confronting the US and Russia in the safe management of excess weapons grade nuclear materials. The US and Russian weapons dismantlement process is producing hundreds of tons of excess Pu and HEU fissile materials. The US is on a two path approach for disposition of excess Pu: (1) use Pu in existing reactors and/or (2) immobilize Pu in glass or ceramics followed by geologic disposal. Russian plans are to fuel reactors with excess Pu. US and Russia are both converting and blending HEU into LEU for use in existing reactors. Fissile nuclear materials storage, handling, processing, and transportation will be occurring in both countries for tens of years. A table provides a history of the major events comprising the Russian-US joint program on the safety of nuclear materials. A paper delineating program efforts was delivered at the SPECTRUM '96 conference. This paper provides an update on program activities since then.

  15. W88 warhead program performs successful tests | National Nuclear Security

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

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  16. Secretary Chu Announces Nuclear Energy University Program Awards |

    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 Energy Power.pdf11-161-LNG |September2-SCORECARD-01-24-13 PageUraniumDepartment of Energy Nuclear

  17. Secretary Chu Announces Nuclear Energy University Program Awards

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

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  18. First Graduates of Nuclear Security Education Program Announced | National

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

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  19. NPO recognized by Defense Programs | National Nuclear Security

    National Nuclear Security Administration (NNSA)

    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) "ofEarlyEnergyDepartmentNational Nuclearhas 'Natitude' | National NuclearAdministrator|News Releases

  20. Senior Adviser, Defense Nuclear Nonproliferation Programs Sector, Pacific

    National Nuclear Security Administration (NNSA)

    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) "ofEarlyEnergyDepartmentNational Nuclearhas 'Natitude'Security AdministrationNuclearFY13UnderNorthwest

  1. Global Nuclear Futures Program Manager, Sandia National Laboratories |

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

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  2. Sandia Weapon Intern Program visits KCP | National Nuclear Security

    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 Administrationcontroller systems controller systemsis a multiprogram laboratory operated by

  3. Small Business Independent Market Research Program | National Nuclear

    National Nuclear Security Administration (NNSA)

    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 ofDepartmentStewardship Science AcademicLaboratory | NationalNuclearUnderMedia1

  4. Sandia National Laboratories: Nuclear Energy and Fuel Systems Programs

    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 Administration the1 -theErik Spoerke SSLSMolten-Salt StorageNo More GreenWorkshops Nuclearand Fuel

  5. Nuclear Fuels Storage and Transportation Planning Project (NFST) Program

    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 Energy Power.pdf11-161-LNG |September 15, 2010 PrintingNeed| Department ofDC. |NuclearFacts:Department

  6. Seventy Years of Computing in the Nuclear Weapons Program

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

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  7. Australian Science and Technology with Relevance to Beamed Energy Propulsion

    SciTech Connect (OSTI)

    Froning, H. David Jr [PO Box 180, Gumeracha SA 5233 (Australia)

    2008-04-28T23:59:59.000Z

    Although Australia has no Beamed Energy Propulsion programs at the present time, it is accomplishing significant scientific and technological activity that is of potential relevance to Beamed Energy Propulsion (BEP). These activities include: continual upgrading and enhancement of the Woomera Test Facility, Which is ideal for development and test of high power laser or microwave systems and the flight vehicles they would propel; collaborative development and test, with the US and UK of hypersonic missiles that embody many features needed by beam-propelled flight vehicles; hypersonic air breathing propulsion systems that embody inlet-engine-nozzle features needed for beam-riding agility by air breathing craft; and research on specially conditioned EM fields that could reduce beamed energy lost during atmospheric propagation.

  8. India's nuclear power program : a study of India's unique approach to nuclear energy

    E-Print Network [OSTI]

    Murray, Caitlin Lenore

    2006-01-01T23:59:59.000Z

    India is in the middle of the biggest expansion of nuclear power in its history, adding 20 GWe in the next 14 years in the form of pressure water reactors and fast breeder reactors. At the same time, the United States is ...

  9. Overview of the Government of Canada Nuclear Legacy Liabilities Program - 13551

    SciTech Connect (OSTI)

    Metcalfe, D.; McCauley, D. [Natural Resources Canada, Ottawa, Ontario, K1A 0E4 (Canada)] [Natural Resources Canada, Ottawa, Ontario, K1A 0E4 (Canada); Miller, J.; Brooks, S. [Atomic Energy of Canada Limited, Chalk River, Ontario, K0J 1J0 (Canada)] [Atomic Energy of Canada Limited, Chalk River, Ontario, K0J 1J0 (Canada)

    2013-07-01T23:59:59.000Z

    Nuclear legacy liabilities have resulted from more than 60 years of nuclear research and development carried out on behalf of Canada. The liabilities are located at Atomic Energy of Canada Limited's (AECL) Chalk River Laboratories in Ontario and Whiteshell Laboratories in Manitoba, as well as three shutdown prototype reactors in Ontario and Quebec that are being maintained in a safe storage state. Estimated at about $7.4 billion (current day dollars), these liabilities consist of disused nuclear facilities and associated infrastructure, a wide variety of buried and stored waste, and contaminated lands. In 2006, the Government of Canada adopted a long-term strategy to deal with the nuclear legacy liabilities and initiated a five-year, $520 million start-up phase, thereby creating the Nuclear Legacy Liabilities Program (NLLP). The Government of Canada renewed the NLLP in 2011 with a $439-million three-year second phase that ends March 31, 2014. The projects and activities carried out under the Program focus on infrastructure decommissioning, environmental restoration, improving the management of legacy radioactive waste, and advancing the long-term strategy. The NLLP is being implemented through a Memorandum of Understanding between Natural Resources Canada (NRCan) and AECL whereby NRCan is responsible for policy direction and oversight, including control of funding, and AECL is responsible for implementing the program of work and holding and administering all licences, facilities and lands. (authors)

  10. Y-12 defense programs: Nuclear Packaging Systems testing capabilities

    SciTech Connect (OSTI)

    NONE

    1995-06-01T23:59:59.000Z

    The Nuclear Packaging Systems (NPS) Department can manage/accomplish any packaging task. The NPS organization is responsible for managing the design, testing, certification, procurement, operation, refurbishment, maintenance, and disposal of packaging used to transport radioactive materials, other hazardous materials, and general cargoes on public roads and within the Oak Ridge Y-12 Plant. Additionally, the NPS Department has developed a Quality Assurance plan for all packaging, design and procurement of nonweapon shipping containers for radioactive materials, and design and procurement of performance-oriented packaging for hazardous materials. Further, the NPS Department is responsible for preparation and submittal of Safety Analysis Reports for Packaging (SARP). The NPS Department coordinates shipping container procurement and safety certification activities that have lead-times of up to two years. A Packaging Testing Capabilities Table at the Oak Ridge complex is included as a table.

  11. Worker Protection Program for DOE (Including the National Nuclear Security Administration) Federal Employees

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

    2007-05-17T23:59:59.000Z

    The Order establishes the framework for an effective worker protection program that will reduce or prevent injuries, illnesses, and accidental losses by providing Department of Energy (DOE), including National Nuclear Security Administration (NNSA), Federal workers with a safe and healthful workplace. Cancels DOE O 440.1A. Certified 6/17/2011. Canceled by DOE O 440.1B Chg 1.

  12. Characterization program management plan for Hanford K basin spent nuclear fuel

    SciTech Connect (OSTI)

    TRIMBLE, D.J.

    1999-07-19T23:59:59.000Z

    The program management plan for characterization of the K Basin spent nuclear fuel was revised to incorporate corrective actions in response to SNF Project QA surveillance 1K-FY-99-060. This revision of the SNF Characterization PMP replaces Duke Eng.

  13. Nuclear Facility Maintenance Management Program Guide for Use with DOE O 433.1B

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

    2011-09-09T23:59:59.000Z

    The guide provides acceptable approaches for implementing requirements for Nuclear Maintenance Management Programs (NMMPs) set forth in DOE O 433.1B. Cancels DOE G 433.1-1. Admin Chg 1, dated 6-14-13, cancels DOE G 433.1-1A.

  14. Project Hanford management contract quality assurance program implementation plan for nuclear facilities

    SciTech Connect (OSTI)

    Bibb, E.K.

    1997-10-15T23:59:59.000Z

    During transition from the Westinghouse Hanford Company (WHC) Management and Operations (M and O) contract to the Fluor Daniel Hanford (FDH) Management and Integration (M and I) contract, existing WHC policies, procedures, and manuals were reviewed to determine which to adopt on an interim basis. Both WHC-SP-1131,Hanford Quality Assurance Program and Implementation Plan, and WHC-CM-4-2, Quality Assurance Manual, were adopted; however, it was recognized that revisions were required to address the functions and responsibilities of the Project Hanford Management Contract (PHMC). This Quality Assurance Program Implementation Plan for Nuclear Facilities (HNF-SP-1228) supersedes the implementation portion of WHC-SP-1 13 1, Rev. 1. The revised Quality Assurance (QA) Program is documented in the Project Hanford Quality Assurance Program Description (QAPD), HNF-MP-599. That document replaces the QA Program in WHC-SP-1131, Rev. 1. The scope of this document is limited to documenting the nuclear facilities managed by FDH and its Major Subcontractors (MSCS) and the status of the implementation of 10 CFR 830.120, Quality Assurance Requirements, at those facilities. Since the QA Program for the nuclear facilities is now documented in the QAPD, future updates of the information provided in this plan will be by letter. The layout of this plan is similar to that of WHC-SP-1 13 1, Rev. 1. Sections 2.0 and 3.0 provide an overview of the Project Hanford QA Program. A list of Project Hanford nuclear facilities is provided in Section 4.0. Section 5.0 provides the status of facility compliance to 10 CFR 830.120. Sections 6.0, 7.0, and 8.0 provide requested exemptions, status of open items, and references, respectively. The four appendices correspond to the four projects that comprise Project Hanford.

  15. Judgment and Decision Making, Vol. 5, No. 7, December 2010, pp. 540546 Sacred values and conflict over Iran's nuclear program

    E-Print Network [OSTI]

    Reber, Paul J.

    over Iran's nuclear program Morteza Dehghani1 , Scott Atran2 , Rumen Iliev3 , Sonya Sachdeva3 , Douglas Research, New York, NY Abstract Conflict over Iran's nuclear program, which involves a US-led policy to impose sanctions on Iran, is perceived by each side as a preeminent challenge to its own national

  16. Military Academy Cadet/Midshipman Program | National Nuclear Security

    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 MayAtmospheric Optical Depth7-1D: VegetationEquipment SurfacesResource Program PreliminaryA3, 1999ofMikeAdministration Academy

  17. EGS 01-01: Nuclear Weapon Program Enforcement Issues

    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 Energy Power SystemsResources DOE ZeroThreeEnergy DrivingD EERE Program ManagementEERE4of

  18. Developments in the Nuclear Safeguards and Security Engineering Degree Program at Tomsk Polytechnic University

    SciTech Connect (OSTI)

    Boiko, Vladimir I.; Demyanyuk, Dmitry G.; Silaev, Maxim E.; Duncan, Cristen L.; Heinberg, Cynthia L.; Killinger, Mark H.; Goodey, Kent O.; Butler, Gilbert W.

    2009-10-06T23:59:59.000Z

    Over the last six years, Tomsk Polytechnic University (TPU) has developed a 5 year engineering degree program in the field of Material Protection Control and Accounting (MPC&A). In 2009 the first students graduated with this new degree. There were 25 job offers from nuclear fuel cycle enterprises of Russia and Kazakhstan for 17 graduates of the program. Due to the rather wide selection of workplaces, all graduates have obtained positions at nuclear enterprises. The program was developed within the Applied Physics and Engineering Department (APED). The laboratory and methodological base has been created taking into consideration the experience of the similar program at the Moscow Engineering Physics Institute (MEPhI). However, the TPU program has some distinguishing features such as the inclusion of special courses pertaining to fuel enrichment and reprocessing. During the last two years, three MPC&A laboratories have been established at APED. This was made possible due to several factors such as establishment of the State innovative educational program at TPU, assistance of the U.S. Department of Energy through Pacific Northwest National Laboratory and Los Alamos National Laboratory, and the financial support of the Swedish Radiation Safety Authority and some Russian private companies. All three of the MPC&A laboratories are part of the Innovative Educational Center Nuclear Technologies and Non-Proliferation, which deals with many topics including research activities, development of new curricula for experts training and retraining, and training of masters students. In 2008, TPU developed a relationship with the International Atomic Energy Agency (IAEA), which was familiarized with APEDs current resources and activities. The IAEA has shown interest in creation of a masters degree educational program in the field of nuclear security at TPU. A future objective is to acquaint nuclear fuel cycle enterprises with new APED capabilities and involve the enterprises in the scientific and educational projects implemented through the Nuclear Technologies and Non-Proliferation Center. This paper describes the development of the MPC&A engineering degree program and future goals of TPU in the field of nonproliferation education.

  19. Nuclear facility decommissioning and site remedial actions: A selected bibliography, Volume 12. Environmental Restoration Program

    SciTech Connect (OSTI)

    Not Available

    1991-09-01T23:59:59.000Z

    The 664 abstracted references on environmental restoration, nuclear facility decommissioning, uranium mill tailings management, and site remedial actions constitute the twelfth in a series of reports prepared annually for the US Department of Energy Remedial Action Programs. Citations to foreign and domestic literature of all types -- technical reports, progress reports, journal articles, symposia proceedings, theses, books, patents, legislation, and research project descriptions -- have been included. The bibliography contains scientific, technical, economic, regulatory, and legal information pertinent to the US Department of Energy Remedial Action Programs. Major sections are (1) Decontamination and Decommissioning Program, (2) Nuclear Facilities Decommissioning, (3) Formerly Utilized Sites Remedial Action Program, (4) Facilities Contaminated with Naturally Occurring Radionuclides, (5) Uranium Mill Tailings Remedial Action Program, (6) Uranium Mill Tailings Management, (7) Technical Measurements Center, and (8) Environmental Restoration Program. Within these categories, references are arranged alphabetically by first author. Those references having no individual author are listed by corporate affiliation or by publication title. Indexes are provided for author, corporate affiliation, title word, publication description, geographic location, subject category, and key word. This report is a product of the Remedial Action Program Information Center (RAPIC), which selects, analyzes, and disseminates information on environmental restoration and remedial actions. RAPIC staff and resources are available to meet a variety of information needs. Contact the center at FTS 624-7764 or (615) 574-7764.

  20. Identification and Analysis of Critical Gaps in Nuclear Fuel Cycle Codes Required by the SINEMA Program

    SciTech Connect (OSTI)

    Adrian Miron; Joshua Valentine; John Christenson; Majd Hawwari; Santosh Bhatt; Mary Lou Dunzik-Gougar: Michael Lineberry

    2009-10-01T23:59:59.000Z

    The current state of the art in nuclear fuel cycle (NFC) modeling is an eclectic mixture of codes with various levels of applicability, flexibility, and availability. In support of the advanced fuel cycle systems analyses, especially those by the Advanced Fuel Cycle Initiative (AFCI), Unviery of Cincinnati in collaboration with Idaho State University carried out a detailed review of the existing codes describing various aspects of the nuclear fuel cycle and identified the research and development needs required for a comprehensive model of the global nuclear energy infrastructure and the associated nuclear fuel cycles. Relevant information obtained on the NFC codes was compiled into a relational database that allows easy access to various codes' properties. Additionally, the research analyzed the gaps in the NFC computer codes with respect to their potential integration into programs that perform comprehensive NFC analysis.

  1. Handbook of nuclear power plant seismic fragilities, Seismic Safety Margins Research Program

    SciTech Connect (OSTI)

    Cover, L.E.; Bohn, M.P.; Campbell, R.D.; Wesley, D.A.

    1983-12-01T23:59:59.000Z

    The Seismic Safety Margins Research Program (SSMRP) has a gola to develop a complete fully coupled analysis procedure (including methods and computer codes) for estimating the risk of an earthquake-induced radioactive release from a commercial nuclear power plant. As part of this program, calculations of the seismic risk from a typical commercial nuclear reactor were made. These calculations required a knowledge of the probability of failure (fragility) of safety-related components in the reactor system which actively participate in the hypothesized accident scenarios. This report describes the development of the required fragility relations and the data sources and data reduction techniques upon which they are based. Both building and component fragilities are covered. The building fragilities are for the Zion Unit 1 reactor which was the specific plant used for development of methodology in the program. Some of the component fragilities are site-specific also, but most would be usable for other sites as well.

  2. Standard guide for establishing a quality assurance program for analytical chemistry laboratories within the nuclear industry

    E-Print Network [OSTI]

    American Society for Testing and Materials. Philadelphia

    2006-01-01T23:59:59.000Z

    1.1 This guide covers the establishment of a quality assurance (QA) program for analytical chemistry laboratories within the nuclear industry. Reference to key elements of ANSI/ISO/ASQC Q9001, Quality Systems, provides guidance to the functional aspects of analytical laboratory operation. When implemented as recommended, the practices presented in this guide will provide a comprehensive QA program for the laboratory. The practices are grouped by functions, which constitute the basic elements of a laboratory QA program. 1.2 The essential, basic elements of a laboratory QA program appear in the following order: Section Organization 5 Quality Assurance Program 6 Training and Qualification 7 Procedures 8 Laboratory Records 9 Control of Records 10 Control of Procurement 11 Control of Measuring Equipment and Materials 12 Control of Measurements 13 Deficiencies and Corrective Actions 14

  3. Nuclear space power safety and facility guidelines study

    SciTech Connect (OSTI)

    Mehlman, W.F.

    1995-09-11T23:59:59.000Z

    This report addresses safety guidelines for space nuclear reactor power missions and was prepared by The Johns Hopkins University Applied Physics Laboratory (JHU/APL) under a Department of Energy grant, DE-FG01-94NE32180 dated 27 September 1994. This grant was based on a proposal submitted by the JHU/APL in response to an {open_quotes}Invitation for Proposals Designed to Support Federal Agencies and Commercial Interests in Meeting Special Power and Propulsion Needs for Future Space Missions{close_quotes}. The United States has not launched a nuclear reactor since SNAP 10A in April 1965 although many Radioisotope Thermoelectric Generators (RTGs) have been launched. An RTG powered system is planned for launch as part of the Cassini mission to Saturn in 1997. Recently the Ballistic Missile Defense Office (BMDO) sponsored the Nuclear Electric Propulsion Space Test Program (NEPSTP) which was to demonstrate and evaluate the Russian-built TOPAZ II nuclear reactor as a power source in space. As of late 1993 the flight portion of this program was canceled but work to investigate the attributes of the reactor were continued but at a reduced level. While the future of space nuclear power systems is uncertain there are potential space missions which would require space nuclear power systems. The differences between space nuclear power systems and RTG devices are sufficient that safety and facility requirements warrant a review in the context of the unique features of a space nuclear reactor power system.

  4. PROPULSION AND ENERGY Terrestrial energy

    E-Print Network [OSTI]

    Aggarwal, Suresh K.

    PROPULSION AND ENERGY Terrestrial energy On the morning of Monday, August 29, Hurri- cane Katrina dependence we all have on power and energy systems. Nine major oil re- fineries in Louisiana and Mississippi- trial energy community is the question of why alternative energy sources, such as coal, solar, wind

  5. Nuclear Waste Treatment Program annual report for FY 1988

    SciTech Connect (OSTI)

    Brouns, R.A.; Powell, J.A. (comps.)

    1989-11-01T23:59:59.000Z

    Much emphasis continues to be on the transfer of remote design technology for components integral to the West Valley Demonstration Project's (WVDP) vitrification process. In addition to preparing equipment specifications and drawings, Pacific Northwest Laboratory (PNL) staff also participated in numerous design coordination meetings and reviews of drawings prepared by other WVDP contractors. Nearly 200 jumper drawings for the vitrification cell were prepared by this program in FY 1988. The remote jumpers connect vessels in the cell to each other for the transfer of solutions and provide for the flow of materials, instrumentation signals, and power from outside the cell. Analysis required in preparing the jumper designs involved balance, thermal stress, seismic, set-down stress, and displacement calculations. Design efforts were begun on the canister decontamination and swipe station and on the remote maintenance station. Equipment selection and layouts of the vitrification off-gas treatment system, including a reamer to remotely clean the melter off-gas line, were finalized. Also finalized were the designs for the high-efficiency particulate air (HEPA) filter assemblies for heating, cooling and air conditioning of the vitrification cell.

  6. General-purpose heat source project and space nuclear safety fuels program. Progress report, February 1980

    SciTech Connect (OSTI)

    Maraman, W.J. (comp.)

    1980-05-01T23:59:59.000Z

    This formal monthly report covers the studies related to the use of /sup 238/PuO/sub 2/ in radioisotopic power systems carried out for the Advanced Nuclear Systems and Projects Division of the Los Alamos Scientific Laboratory. The two programs involved are: General-Purpose Heat Source Development and Space Nuclear Safety and Fuels. Most of the studies discussed here are of a continuing nature. Results and conclusions described may change as the work continues. Published reference to the results cited in this report should not be made without the explicit permission of the person in charge of the work.

  7. Reproduced with permission of the copyright owner. Further reproduction prohibited without permission. Overcoming tunnel vision: Redirecting the U.S. high-level nuclear waste program

    E-Print Network [OSTI]

    Kammen, Daniel M.

    permission. Overcoming tunnel vision: Redirecting the U.S. high-level nuclear waste program James Flynn

  8. National Nuclear Security Administration Nonproliferation Graduate Fellowship Program Annual Report in Brief: October 2007 - May 2008

    SciTech Connect (OSTI)

    Berkman, Clarissa O.; Fankhauser, Jana G.; Sandusky, Jessica A.

    2009-05-01T23:59:59.000Z

    This abbreviated Annual Report covers program activities of the National Nuclear Security Administration (NNSA) Nonproliferation Graduate Fellowship Program (NGFP) from October 2007 through May 2008--the timeframe between the last Annual Report (which covered activities through September 2007) and the next report (which will begin with June 2008 activities). In that timeframe, the NGFP continued building a solid foundation as the program began reaping the benefits of recently implemented changes. This report is organized by Fellowship class and the pertinent program activities for each, including: October 2007 Recruiting events and final applications (Class of 2008) Winter 2007 Selection and hiring (Class of 2008) Spring 2008 Career development roundtables (Class of 2007) Orientation planning (Class of 2008) Recruitment planning and university outreach (Class of 2009) May 2008 Closing ceremony (Class of 2007)

  9. Radioisotope electric propulsion of sciencecraft to the outer solar system and near-interstellar space

    SciTech Connect (OSTI)

    Noble, R.J.

    1998-08-01T23:59:59.000Z

    Recent results are presented in the study of radioisotope electric propulsion as a near-term technology for sending small robotic sciencecraft to the outer Solar System and near-interstellar space. Radioisotope electric propulsion (REP) systems are low-thrust, ion propulsion units based on radioisotope electric generators and ion thrusters. Powerplant specific masses are expected to be in the range of 100 to 200 kg/kW of thrust power. Planetary rendezvous missions to Pluto, fast missions to the heliopause (100 AU) with the capability to decelerate an orbiter for an extended science program and prestellar missions to the first gravitational lens focus of the Sun (550 AU) are investigated.

  10. Advanced ignition and propulsion technology program

    SciTech Connect (OSTI)

    Oldenborg, R.; Early, J.; Lester, C.

    1998-11-01T23:59:59.000Z

    This is the final report of a three-year, Laboratory Directed Research and Development (LDRD) project at the Los Alamos National Laboratory (LANL). Reliable engine re-ignition plays a crucial role in enabling commercial and military aircraft to fly safely at high altitudes. This project addressed research elements critical to the optimization of laser-based igniter. The effort initially involved a collaborative research and development agreement with B.F. Goodrich Aerospace and Laser Fare, Inc. The work involved integrated experiments with theoretical modeling to provide a basic understanding of the chemistry and physics controlling the laser-induced ignition of fuel aerosols produced by turbojet engine injectors. In addition, the authors defined advanced laser igniter configurations that minimize laser packaging size, weight, complexity and power consumption. These innovative ignition concepts were shown to reliably ignite jet fuel aerosols over a broad range of fuel/air mixture and a t fuel temperatures as low as -40 deg F. The demonstrated fuel ignition performance was highly superior to that obtained by the state-of-the-art, laser-spark ignition method utilizing comparable laser energy. The authors also developed a laser-based method that effectively removes optically opaque deposits of fuel hydrocarbon combustion residues from laser window surfaces. Seven patents have been either issued or are pending that resulted from the technology developments within this project.

  11. Required Assets for a Nuclear Energy Applied R&D Program

    SciTech Connect (OSTI)

    Harold F. McFarlane; Craig L. Jacobson

    2009-03-01T23:59:59.000Z

    This report is one of a set of three documents that have collectively identified and recommended research and development capabilities that will be required to advance nuclear energy in the next 20 to 50 years. The first report, Nuclear Energy for the Future: Required Research and Development CapabilitiesAn Industry Perspective, was produced by Battelle Memorial Institute at the request of the Assistant Secretary of Nuclear Energy. That report, drawn from input by industry, academia, and Department of Energy laboratories, can be found in Appendix 5.1. This Idaho National Laboratory report maps the nuclear-specific capabilities from the Battelle report onto facility requirements, identifying options from the set of national laboratory, university, industry, and international facilities. It also identifies significant gaps in the required facility capabilities. The third document, Executive Recommendations for Nuclear R&D Capabilities, is a letter report containing a set of recommendations made by a team of senior executives representing nuclear vendors, utilities, academia, and the national laboratories (at Battelles request). That third report can be found in Appendix 5.2. The three reports should be considered as set in order to have a more complete picture. The basis of this report was drawn from three sources: previous Department of Energy reports, workshops and committee meetings, and expert opinion. The facilities discussed were winnowed from several hundred facilities that had previously been catalogued and several additional facilities that had been overlooked in past exercises. The scope of this report is limited to commercial nuclear energy and those things the federal government, or more specifically the Office of Nuclear Energy, should do to support its expanded deployment in order to increase energy security and reduce carbon emissions. In the context of this report, capabilities mean innovative, well-structured research and development programs, a viable work force, and well-equipped specialized facilities.

  12. Yucca Mountain: How Do Global and Federal Initiatives Impact Clark County's Nuclear Waste Program?

    SciTech Connect (OSTI)

    Navis, I.; McGehee, B. [Clark County Department of Comprehensive Planning - Nuclear Waste Division, Las Vegas, NV (United States)

    2008-07-01T23:59:59.000Z

    Since 1987, Clark County has been designated by the U.S. Department of Energy (DOE) as an 'Affected Unit of Local Government' (AULG). The AULG designation is an acknowledgement by the federal government that activities associated with the Yucca Mountain proposal could result in considerable impacts on Clark County residents and the community as a whole. As an AULG, Clark County is authorized to identify 'any potential economic, social, public health and safety, and environmental impacts of a repository', 42 U.S.C. Section 10135(c)(1)(B)(i) under provisions of the Nuclear Waste Policy Act Amendments (NWPAA). Clark County's oversight program contains key elements of (1) technical and scientific analysis (2) transportation analysis (3) impact assessment and monitoring (4) policy and legislative analysis and monitoring, and (5) public outreach. Clark County has conducted numerous studies of potential impacts, many of which are summarized in Clark County's Impact Assessment Report that was submitted DOE and the President of the United States in February 2002. Given the unprecedented magnitude and duration of DOE's proposal, as well as the many unanswered questions about the transportation routes, number of shipments, and the modal mix that will ultimately be used, impacts to public health and safety and security, as well as socioeconomic impacts, can only be estimated. In order to refine these estimates, Clark County Comprehensive Planning Department's Nuclear Waste Division updates, assesses, and monitors impacts on a regular basis. Clark County's Impact Assessment program covers not only unincorporated Clark County but all five jurisdictions of Las Vegas, North Las Vegas, Henderson, Mesquite, and Boulder City as well as tribal jurisdictions that fall within Clark County's geographic boundary. National and global focus on nuclear power and nuclear waste could have significant impact on the Yucca Mountain Program, and therefore, Clark County's oversight of that program. (authors)

  13. The Soviet program for peaceful uses of nuclear explosions. Revision 1

    SciTech Connect (OSTI)

    Nordyke, M.D.

    1996-10-01T23:59:59.000Z

    An extensive review is given of the US and Russian efforts on peaceful uses of nuclear explosions (PNE). The Soviet PNE program was many times larger than the US Plowshare program in terms of both the number of applications explored with field experiments and the extent to which they were introduced into industrial use. Several PNE applications, such as deep seismic sounding and oil stimulation, have been explored in depth and appear to have had a positive cost benefit at minimal public risk. Closure of runaway gas wells is another possible application where all other techniques fail. However, the fundamental problem with PNEs is the fact that, if they are to be economically significant, there must be widespread use of the technology, involving large numbers of sites, each of which presents a potential source of radioactivity to the environment and nearby communities. Russia now has more than 100 sites where significant high-level radioactivity has been buried. Experience over the last 20 years in US and in today`s Russia shows that it is virtually impossible to gain public acceptance of such applications of nuclear energy. In addition, PNEs also pose a difficult problem in the arms control area. Under a comprehensive test ban, any country conducting PNEs would, in appearance if not in fact, receive information useful for designing new nuclear weapons or maintaining an existing nuclear stockpile, information denied to the other parties to the treaty. 6 tabs, 10 figs.

  14. for Nuclear Energy Undergraduate Scholarships Subject: Integrated University Program: Undergraduate Scholarship Program - RFA

    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 EnergyEnergyENERGYWomen Owned SmallOf TheViolations |JoinZero-Energy Home1-14 for Nuclear Energy

  15. UMCP-BG and E collaboration in nuclear power engineering in the framework of DOE-Utility Nuclear Power Engineering Education Matching Grant Program

    SciTech Connect (OSTI)

    Wolfe, Lothar PhD

    2000-03-01T23:59:59.000Z

    The DOE-Utility Nuclear Power Engineering Education Matching Grant Program has been established to support the education of students in Nuclear Engineering Programs to maintain a knowledgeable workforce in the United States in order to keep nuclear power as a viable component in a mix of energy sources for the country. The involvement of the utility industry ensures that this grant program satisfies the needs and requirements of local nuclear energy producers and at the same time establishes a strong linkage between education and day-to-day nuclear power generation. As of 1997, seventeen pairs of university-utility partners existed. UMCP was never a member of that group of universities, but applied for the first time with a proposal to Baltimore Gas and Electric Company in January 1999 [1]. This proposal was generously granted by BG&E [2,3] in the form of a gift in the amount of $25,000 from BG&E's Corporate Contribution Program. Upon the arrival of a newly appointed Director of Administration in the Department of Materials and Nuclear Engineering, the BG&E check was deposited into the University's Maryland Foundation Fund. The receipt of the letter and the check enabled UMCP to apply for DOE's matching funds in the same amount by a proposal.

  16. Structural aging program to assess the adequacy of critical concrete components in nuclear power plants

    SciTech Connect (OSTI)

    Naus, D.J.; Marchbanks, M.F.; Oland, C.B.; Arndt, E.G.

    1989-01-01T23:59:59.000Z

    The Structural Aging (SAG) Program is carried out by the Oak Ridge National Laboratory (ORNL) under sponsorship of the United States Nuclear Regulatory Commission (USNRC). The Program has evolved from preliminary studies conducted to evaluate the long-term environmental challenges to light-water reactor safety-related concrete civil structures. An important conclusion of these studies was that a damage methodology, which can provide a quantitative measure of a concrete structure's durability with respect to potential future requirements, needs to be developed. Under the SAG Program, this issue is being addressed through: establishment of a structural materials information center, evaluation of structural component assessment and repair technologies, and development of a quantitative methodology for structural aging determinations. Progress to date of each of these activities is presented as well as future plans. 7 refs., 5 figs.

  17. Programs for the work with ENSDF format files: Evaluator's editor EVE, Viewer for the nuclear level schemes

    E-Print Network [OSTI]

    G. I. Shulyak; A. A. Rodionov

    2010-04-19T23:59:59.000Z

    Tools for the regular work of the nuclear data evaluator are presented: the context-dependent editor EVE and the viewer for the level schemes of nuclei from ENSDF datasets. These programs may be used by everybody who works with the Evaluated Nuclear Structure Data File and for the educational purposed.

  18. Historical Perspective on the United States Fusion Program Invited paper presented at American Nuclear Society 16th

    E-Print Network [OSTI]

    controlled thermonuclear reactions, or nuclear fusion as it is now more commonly called, has remained elusiveHistorical Perspective on the United States Fusion Program Invited paper presented at American Nuclear Society 16th Topical Meeting on the Technology of Fusion Energy 14-16 September, 2004 in Madison

  19. 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.

  20. Generation IV Nuclear Energy Systems Ten-Year Program Plan Fiscal Year 2005, Volume 1

    SciTech Connect (OSTI)

    None

    2005-03-01T23:59:59.000Z

    As reflected in the U.S. ''National Energy Policy'', nuclear energy has a strong role to play in satisfying our nation's future energy security and environmental quality needs. The desirable environmental, economic, and sustainability attributes of nuclear energy give it a cornerstone position, not only in the U.S. energy portfolio, but also in the world's future energy portfolio. Accordingly, on September 20, 2002, U.S. Energy Secretary Spencer Abraham announced that, ''The United States and nine other countries have agreed to develop six Generation IV nuclear energy concepts''. The Secretary also noted that the systems are expected to ''represent significant advances in economics, safety, reliability, proliferation resistance, and waste minimization''. The six systems and their broad, worldwide research and development (R&D) needs are described in ''A Technology Roadmap for Generation IV Nuclear Energy Systems'' (hereafter referred to as the Generation IV Roadmap). The first 10 years of required U.S. R&D contributions to achieve the goals described in the Generation IV Roadmap are outlined in this Program Plan.

  1. 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...

  2. NWTS program criteria for mined geologic disposal of nuclear waste: program objectives, functional requirements, and system performance criteria

    SciTech Connect (OSTI)

    None

    1981-04-01T23:59:59.000Z

    At the present time, final repository criteria have not been issued by the responsible agencies. This document describes general objectives, requirements, and criteria that the DOE intends to apply in the interim to the National Waste Terminal Storage (NWTS) Program. These objectives, requirements, and criteria have been developed on the basis of DOE's analysis of what is needed to achieve the National objective of safe waste disposal in an environmentally acceptable and economic manner and are expected to be consistent with anticipated regulatory standards. The qualitative statements in this document address the broad issues of public and occupational health and safety, institutional acceptability, engineering feasibility, and economic considerations. A comprehensive set of criteria, general and project specific, of which these are a part, will constitute a portion of the technical basis for preparation and submittal by the DOE of formal documents to support future license applications for nuclear waste repositories.

  3. Autonomous Intelligent Hybrid Propulsion Systems

    Broader source: Energy.gov [DOE]

    2013 DOE Hydrogen and Fuel Cells Program and Vehicle Technologies Program Annual Merit Review and Peer Evaluation Meeting

  4. An underground characterization program for a nuclear fuel waste disposal vault in plutonic rock

    SciTech Connect (OSTI)

    Thompson, P.M.; Everitt, R.A. [AECL Research, Pinawa, Manitoba (Canada). Whiteshell Labs.

    1993-12-31T23:59:59.000Z

    The Canadian Nuclear Fuel Waste Management Program (CNFWMP) is developing a concept for disposing of nuclear fuel waste that involves placing and sealing it in a disposal vault excavated 500 to 1,000 m deep in the stable plutonic rock of the Canadian Shield. In this concept, engineered and natural barriers serve to isolate the waste from the biosphere. Since 1983, underground characterization and testing in support of the CNFWMP has been ongoing at the Underground Research Laboratory (URL) in southeastern Manitoba. This paper draws on experience gained at the URL to recommend an approach to underground characterization that would provide the necessary information to make design decisions for a disposal vault in plutonic rock.

  5. Sandia National Laboratories support of the Iraq Nuclear Facility Dismantlement and Disposal Program.

    SciTech Connect (OSTI)

    Cochran, John Russell; Danneels, Jeffrey John

    2009-03-01T23:59:59.000Z

    Because of past military operations, lack of upkeep and looting there are now enormous radioactive waste problems in Iraq. These waste problems include destroyed nuclear facilities, uncharacterized radioactive wastes, liquid radioactive waste in underground tanks, wastes related to the production of yellow cake, sealed radioactive sources, activated metals and contaminated metals that must be constantly guarded. Iraq currently lacks the trained personnel, regulatory and physical infrastructure to safely and securely manage these facilities and wastes. In 2005 the International Atomic Energy Agency (IAEA) agreed to organize an international cooperative program to assist Iraq with these issues. Soon after, the Iraq Nuclear Facility Dismantlement and Disposal Program (the NDs Program) was initiated by the U.S. Department of State (DOS) to support the IAEA and assist the Government of Iraq (GOI) in eliminating the threats from poorly controlled radioactive materials. The Iraq NDs Program is providing support for the IAEA plus training, consultation and limited equipment to the GOI. The GOI owns the problems and will be responsible for implementation of the Iraq NDs Program. Sandia National Laboratories (Sandia) is a part of the DOS's team implementing the Iraq NDs Program. This report documents Sandia's support of the Iraq NDs Program, which has developed into three principal work streams: (1) training and technical consultation; (2) introducing Iraqis to modern decommissioning and waste management practices; and (3) supporting the IAEA, as they assist the GOI. Examples of each of these work streams include: (1) presentation of a three-day training workshop on 'Practical Concepts for Safe Disposal of Low-Level Radioactive Waste in Arid Settings;' (2) leading GOI representatives on a tour of two operating low level radioactive waste disposal facilities in the U.S.; and (3) supporting the IAEA's Technical Meeting with the GOI from April 21-25, 2008. As noted in the report, there was significant teaming between the various participants to best help the GOI. On-the-ground progress is the focus of the Iraq NDs Program and much of the work is a transfer of technical and practical skills and knowledge that Sandia uses day-to-day. On-the-ground progress was achieved in July of 2008 when the GOI began the physical cleanup and dismantlement of the Active Metallurgical Testing Laboratory (LAMA) facility at Al Tuwaitha, near Baghdad.

  6. Research, development, and demonstration of lead-acid batteries for electric vehicle propulsion. Annual report, 1980

    SciTech Connect (OSTI)

    Not Available

    1981-03-01T23:59:59.000Z

    The progress and status of Eltra's Electric Vehicle Battery Program during FY-80 are presented under five divisional headings: Research on Components and Processes; Development of Cells and Modules for Electric Vehicle Propulsion; Sub-Systems; Pilot Line Production of Electric Vehicle Battery Prototypes; and Program Management.

  7. Robert C. Seamans, Jr. Appointed to Lead Nuclear Weapons Program | National

    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 Administration the1 -the Mid-Infrared0 Resource Program SeptemberRobert B. Laughlin, 1984 TheRobert

  8. Robotics program gets boost from $10,000 donation | National Nuclear

    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 Administration the1 -the Mid-Infrared0 Resource Program SeptemberRobertIntelligent System

  9. Center for Turbulence Research Proceedings of the Summer Program 2008

    E-Print Network [OSTI]

    Prinz, Friedrich B.

    simulation of a hypersonic vehicle with scramjet propulsion system. The papers in this group cover important of the Summer Program: Scramjet Propulsion (A. Auslender); Numerical Methods for Complex Flows (F. Ham

  10. DOE Vehicle Technologies Program 2009 Merit Review Report - Lightweigh...

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

    6.pdf More Documents & Publications DOE Vehicle Technologies Program 2009 Merit Review Report - Propulsion Materials DOE Vehicle Technologies Program 2009 Merit Review Report -...

  11. DOE Vehicle Technologies Program 2009 Merit Review Report - Advanced...

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

    4.pdf More Documents & Publications DOE Vehicle Technologies Program 2009 Merit Review Report - Propulsion Materials DOE Vehicle Technologies Program 2009 Merit Review Report -...

  12. SciTech Connect: Hydrogen peroxide propulsion for smaller satellites...

    Office of Scientific and Technical Information (OSTI)

    Conference: Hydrogen peroxide propulsion for smaller satellites (SSC98-VIII-1) Citation Details In-Document Search Title: Hydrogen peroxide propulsion for smaller satellites...

  13. Vehicle Technologies Office: 2010 Propulsion Materials R&D Annual...

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

    0 Propulsion Materials R&D Annual Progress Report Vehicle Technologies Office: 2010 Propulsion Materials R&D Annual Progress Report 2010 annual progress report focusing on enabling...

  14. Vehicle Technologies Office: 2008 Propulsion Materials R&D Annual...

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

    8 Propulsion Materials R&D Annual Progress Report Vehicle Technologies Office: 2008 Propulsion Materials R&D Annual Progress Report 2008propulsionmaterials.pdf More Documents &...

  15. Vehicle Technologies Office: 2011 Propulsion Materials R&D Annual...

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

    Vehicle Technologies Office: 2011 Propulsion Materials R&D Annual Progress Report Vehicle Technologies Office: 2011 Propulsion Materials R&D Annual Progress Report 2011 annual...

  16. Vehicle Technologies Office: 2012 Propulsion Materials R&D Annual...

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

    2012 Propulsion Materials R&D Annual Progress Report Vehicle Technologies Office: 2012 Propulsion Materials R&D Annual Progress Report 2012 annual progress report focusing on...

  17. Vehicle Technologies Office: 2013 Propulsion Materials R&D Annual...

    Energy Savers [EERE]

    3 Propulsion Materials R&D Annual Progress Report Vehicle Technologies Office: 2013 Propulsion Materials R&D Annual Progress Report This report describes the progress made during...

  18. Enabling Green Energy and Propulsion Systems via Direct Noise...

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

    GE propulsion systems Enabling Green Energy and Propulsion Systems via Direct Noise Computation PI Name: Umesh Paliath PI Email: paliath@ge.com Institution: GE Global Research...

  19. 2008 Annual Merit Review Results Summary - 12. Propulsion Materials...

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

    2008 Annual Merit Review Results Summary - 12. Propulsion Materials 2008 Annual Merit Review Results Summary - 12. Propulsion Materials DOE Vehicle Technologies Annual Merit Review...

  20. Vehicle Technologies Office: 2009 Propulsion Materials R&D Annual...

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

    9 Propulsion Materials R&D Annual Progress Report Vehicle Technologies Office: 2009 Propulsion Materials R&D Annual Progress Report 2009propulsionmaterials.pdf More Documents &...

  1. Nuclear Physics

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

    Underground Research Facility in South Dakota, which will search for neutrinoless double-beta decay. Strong Los Alamos programs in nuclear data and nuclear theory supports...

  2. General-purpose heat source project and space nuclear safety and fuels program. Progress report

    SciTech Connect (OSTI)

    Maraman, W.J.

    1980-02-01T23:59:59.000Z

    Studies related to the use of /sup 238/PuO/sub 2/ in radioisotopic power systems carried out for the Advanced Nuclear Systems and Projects Division of LASL are presented. The three programs involved are: general-purpose heat source development; space nuclear safety; and fuels program. Three impact tests were conducted to evaluate the effects of a high temperature reentry pulse and the use of CBCF on impact performance. Additionally, two /sup 238/PuO/sub 2/ pellets were encapsulated in Ir-0.3% W for impact testing. Results of the clad development test and vent testing are noted. Results of the environmental tests are summarized. Progress on the Stirling isotope power systems test and the status of the improved MHW tests are indicated. The examination of the impact failure of the iridium shell of MHFT-65 at a fuel pass-through continued. A test plan was written for vibration testing of the assembled light-weight radioisotopic heater unit. Progress on fuel processing is reported.

  3. North Korea's nuclear weapons program:verification priorities and new challenges.

    SciTech Connect (OSTI)

    Moon, Duk-ho (Korean Consulate General in New York)

    2003-12-01T23:59:59.000Z

    A comprehensive settlement of the North Korean nuclear issue may involve military, economic, political, and diplomatic components, many of which will require verification to ensure reciprocal implementation. This paper sets out potential verification methodologies that might address a wide range of objectives. The inspection requirements set by the International Atomic Energy Agency form the foundation, first as defined at the time of the Agreed Framework in 1994, and now as modified by the events since revelation of the North Korean uranium enrichment program in October 2002. In addition, refreezing the reprocessing facility and 5 MWe reactor, taking possession of possible weapons components and destroying weaponization capabilities add many new verification tasks. The paper also considers several measures for the short-term freezing of the North's nuclear weapon program during the process of negotiations, should that process be protracted. New inspection technologies and monitoring tools are applicable to North Korean facilities and may offer improved approaches over those envisioned just a few years ago. These are noted, and potential bilateral and regional verification regimes are examined.

  4. Technical and Political Assessment of Peaceful Nuclear Power Program Prospects in North Africa and the Middle East

    SciTech Connect (OSTI)

    Windsor, Lindsay K.; Kessler, Carol E.

    2007-09-11T23:59:59.000Z

    An exceptional number of Middle Eastern and North African nations have recently expressed interest in developing nuclear energy for peaceful purposes. Many of these countries have explored nuclear research in limited ways in the past, but the current focused interest and application of resources towards developing nuclear-generated electricity and nuclear-powered desalination plants is unprecedented. Consequently, questions arise in response to this emerging trend: What instigated this interest? To what end(s) will a nuclear program be applied? Does the country have adequate technical, political, legislative, nonproliferation, and safety infrastructure required for the capability desired? If so, what are the next steps for a country in preparation for a future nuclear program? And if not, what collaboration efforts are possible with the United States or others? This report provides information on the capabilities and interests of 13 countries in the region in nuclear energy programs in light of safety, nonproliferation and security concerns. It also provides information useful for determining potential for offering technical collaboration, financial aid, and/or political support.

  5. DOE/DHS INDUSTRIAL CONTROL SYSTEM CYBER SECURITY PROGRAMS: A MODEL FOR USE IN NUCLEAR FACILITY SAFEGUARDS AND SECURITY

    SciTech Connect (OSTI)

    Robert S. Anderson; Mark Schanfein; Trond Bjornard; Paul Moskowitz

    2011-07-01T23:59:59.000Z

    Many critical infrastructure sectors have been investigating cyber security issues for several years especially with the help of two primary government programs. The U.S. Department of Energy (DOE) National SCADA Test Bed and the U.S. Department of Homeland Security (DHS) Control Systems Security Program have both implemented activities aimed at securing the industrial control systems that operate the North American electric grid along with several other critical infrastructure sectors (ICS). These programs have spent the last seven years working with industry including asset owners, educational institutions, standards and regulating bodies, and control system vendors. The programs common mission is to provide outreach, identification of cyber vulnerabilities to ICS and mitigation strategies to enhance security postures. The success of these programs indicates that a similar approach can be successfully translated into other sectors including nuclear operations, safeguards, and security. The industry regulating bodies have included cyber security requirements and in some cases, have incorporated sets of standards with penalties for non-compliance such as the North American Electric Reliability Corporation Critical Infrastructure Protection standards. These DOE and DHS programs that address security improvements by both suppliers and end users provide an excellent model for nuclear facility personnel concerned with safeguards and security cyber vulnerabilities and countermeasures. It is not a stretch to imagine complete surreptitious collapse of protection against the removal of nuclear material or even initiation of a criticality event as witnessed at Three Mile Island or Chernobyl in a nuclear ICS inadequately protected against the cyber threat.

  6. NRC Technical Research Program to Evaluate Extended Storage and Transportation of Spent Nuclear Fuel - 12547

    SciTech Connect (OSTI)

    Einziger, R.E.; Compton, K.; Gordon, M.; Ahn, T.; Gonzales, H. [United States Nuclear Regulatory Commission, Rockville, Maryland 20852 (United States); Pan, Y. [Center for Nuclear Waste Regulatory Analyses, San Antonio, TX 78238 (United States)

    2012-07-01T23:59:59.000Z

    Any new direction proposed for the back-end of spent nuclear fuel (SNF) cycle will require storage of SNF beyond the current licensing periods. The Nuclear Regulatory Commission (NRC) has established a technical research program to determine if any changes in the 10 CFR part 71, and 72 requirements, and associated guidance might be necessary to regulate the safety of anticipated extended storage, and subsequent transport of SNF. This three part program of: 1) analysis of knowledge gaps in the potential degradation of materials, 2) short-term research and modeling, and 3) long-term demonstration of systems, will allow the NRC to make informed regulatory changes, and determine when and if additional monitoring and inspection of the systems is necessary. The NRC has started a research program to obtain data necessary to determine if the current regulatory guidance is sufficient if interim dry storage has to be extended beyond the currently approved licensing periods. The three-phased approach consists of: - the identification and prioritization of potential degradation of the components related to the safe operation of a dry cask storage system, - short-term research to determine if the initial analysis was correct, and - a long-term prototypic demonstration project to confirm the models and results obtained in the short-term research. The gap analysis has identified issues with the SCC of the stainless steel canisters, and SNF behavior. Issues impacting the SNF and canister internal performance such as high and low temperature distributions, and drying have also been identified. Research to evaluate these issues is underway. Evaluations have been conducted to determine the relative values that various types of long-term demonstration projects might provide. These projects or follow-on work is expected to continue over the next five years. (authors)

  7. Safety research programs sponsored by Office of Nuclear Regulatory Research: Progress report, January 1--March 31, 1989

    SciTech Connect (OSTI)

    Weiss, A.J. (comp.)

    1989-08-01T23:59:59.000Z

    This progress report describes current activities and technical progress in the programs at Brookhaven National Laboratory sponsored by the Division of Regulatory Applications, Division of Engineering, Division of Safety Issue Resolution, and Division of Systems Research of the US Nuclear Regulatory Commission, Office of Nuclear Regulatory Research following the reorganization in July 1988. The previous reports have covered the period October 1, 1976 through December 31, 1988.

  8. Heavy Vehicle Propulsion Materials: Recent Progress and Future Plans

    SciTech Connect (OSTI)

    D. Ray Johnson; Sidney Diamond

    2001-05-14T23:59:59.000Z

    The Heavy Vehicle Propulsion Materials Program provides enabling materials technology for the U.S. DOE Office of Heavy Vehicle Technologies (OHVT). The technical agenda for the program is based on an industry assessment and the technology roadmap for the OHVT. A five-year program plan was published in 2000. Major efforts in the program are materials for diesel engine fuel systems, exhaust aftertreatment, and air handling. Additional efforts include diesel engine valve-train materials, structural components, and thermal management. Advanced materials, including high-temperature metal alloys, intermetallics, cermets, ceramics, amorphous materials, metal- and ceramic-matrix composites, and coatings, are investigated for critical engine applications. Selected technical issues and planned and ongoing projects as well as brief summaries of several technical highlights are given.

  9. Development of a Plasma Probe Positioner Positioner for Propulsion Research

    E-Print Network [OSTI]

    Petta, Jason

    (real-time, no delay) electric motor that divides a full rotation into a large number of steps1. #12 Advisor: Dr. Edgar Choueiri Mentor: Luke Uribarri #12;PPDyL 2 Outline Spacecraft Propulsion Electric vs. Chemical Propulsion How Electric Propulsion uses Plasma Problem with Electric Propulsion : Onset Solution

  10. Integration of Electric Propulsion Systems with Spacecraft An Overview

    E-Print Network [OSTI]

    Walker, Mitchell

    electric propulsion systems are currently being developed ­ ranging from high-power (i.e., >10 kW) systems-propulsion systems to be used on small satellites? In the context of direct-drive electric propulsion? 1 Research1 Integration of Electric Propulsion Systems with Spacecraft ­ An Overview Thomas M. Liu1

  11. Application of a neptune propulsion concept to a manned mars excursion. Master's thesis

    SciTech Connect (OSTI)

    Finley, C.J.

    1993-04-01T23:59:59.000Z

    NEPTUNE is a multimegawatt electric propulsion system. It uses a proven compact nuclear thermal rocket, NERVA, in a closed cycle with a magnetohydrodynamic (MHD) generator to power a magnetoplasmadynamic (MPD) thruster. This thesis defines constraints on an externally sourced propulsion system intended to carry out a manned Martian excursion. It assesses NEPTUNE's ability to conform to these constraints. Because an unmodified NEPTUNE system is too large, the thesis develops modifications to the system which reduce its size. The result is a far less proven, but more useful derivative of the unmodified NEPTUNE system.

  12. Problems in developing bimodal space power and propulsion system fuel element

    SciTech Connect (OSTI)

    Nikolaev, Yu. V.; Gontar, A. S.; Zaznoba, V. A.; Parshin, N. Ya.; Ponomarev-Stepnoi, N. N.; Usov, V. A. [Research Institute of SIA 'Lutch' Podolsk, Moscow Region, 142100 (Russian Federation); RRC 'Kurchatov Institute' Moscow, 123182 (Russian Federation)

    1997-01-10T23:59:59.000Z

    The paper discusses design of a space nuclear power and propulsion system fuel element (PPFE) developed on the basis of an enhanced single-cell thermionic fuel element (TFE) of the 'TOPAZ-2' thermionic converter-reactor (TCR), and presents the PPFE performance for propulsion and power modes of operation. The choice of UC-TaC fuel composition is substantiated. Data on hydrogen effect on the PPFE output voltage are presented, design solutions are considered that allow to restrict hydrogen supply to an interelectrode gap (IEG). Long-term geometric stability of an emitter assembly is supported by calculated data.

  13. Sandia National Laboratories: Solar Electric Propulsion

    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 Administration the1 -theErikGroundbreaking WorkTransformationSiting SitingProgramsAdvanced Nuclear

  14. Next Generation Nuclear Plant Methods Research and Development Technical Program Plan -- PLN-2498

    SciTech Connect (OSTI)

    Richard R. Schultz; Abderrafi M. Ougouag; David W. Nigg; Hans D. Gougar; Richard W. Johnson; William K. Terry; Chang H. Oh; Donald W. McEligot; Gary W. Johnsen; Glenn E. McCreery; Woo Y. Yoon; James W. Sterbentz; J. Steve Herring; Temitope A. Taiwo; Thomas Y. C. Wei; William D. Pointer; Won S. Yang; Michael T. Farmer; Hussein S. Khalil; Madeline A. Feltus

    2008-09-01T23:59:59.000Z

    One of the great challenges of designing and licensing the Very High Temperature Reactor (VHTR) is to confirm that the intended VHTR analysis tools can be used confidently to make decisions and to assure all that the reactor systems are safe and meet the performance objectives of the Generation IV Program. The research and development (R&D) projects defined in the Next Generation Nuclear Plant (NGNP) Design Methods Development and Validation Program will ensure that the tools used to perform the required calculations and analyses can be trusted. The Methods R&D tasks are designed to ensure that the calculational envelope of the tools used to analyze the VHTR reactor systems encompasses, or is larger than, the operational and transient envelope of the VHTR itself. The Methods R&D focuses on the development of tools to assess the neutronic and thermal fluid behavior of the plant. The fuel behavior and fission product transport models are discussed in the Advanced Gas Reactor (AGR) program plan. Various stress analysis and mechanical design tools will also need to be developed and validated and will ultimately also be included in the Methods R&D Program Plan. The calculational envelope of the neutronics and thermal-fluids software tools intended to be used on the NGNP is defined by the scenarios and phenomena that these tools can calculate with confidence. The software tools can only be used confidently when the results they produce have been shown to be in reasonable agreement with first-principle results, thought-problems, and data that describe the highly ranked phenomena inherent in all operational conditions and important accident scenarios for the VHTR.

  15. 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.

  16. Department of Energy Programmatic Spent Nuclear Fuel Management and Idaho National Engineering Laboratory Environmental Restoration and Waste Management Programs Draft Environmental Impact Statement. Volume 1, Appendix C, Savannah River Site Spent Nuclear Fuel Mangement Program

    SciTech Connect (OSTI)

    Not Available

    1994-06-01T23:59:59.000Z

    The US Department of Energy (DOE) is engaged in two related decision making processes concerning: (1) the transportation, receipt, processing, and storage of spent nuclear fuel (SNF) at the DOE Idaho National Engineering Laboratory (INEL) which will focus on the next 10 years; and (2) programmatic decisions on future spent nuclear fuel management which will emphasize the next 40 years. DOE is analyzing the environmental consequences of these spent nuclear fuel management actions in this two-volume Environmental Impact Statement (EIS). Volume 1 supports broad programmatic decisions that will have applicability across the DOE complex and describes in detail the purpose and need for this DOE action. Volume 2 is specific to actions at the INEL. This document, which limits its discussion to the Savannah River Site (SRS) spent nuclear fuel management program, supports Volume 1 of the EIS. Following the introduction, Chapter 2 contains background information related to the SRS and the framework of environmental regulations pertinent to spent nuclear fuel management. Chapter 3 identifies spent nuclear fuel management alternatives that DOE could implement at the SRS, and summarizes their potential environmental consequences. Chapter 4 describes the existing environmental resources of the SRS that spent nuclear fuel activities could affect. Chapter 5 analyzes in detail the environmental consequences of each spent nuclear fuel management alternative and describes cumulative impacts. The chapter also contains information on unavoidable adverse impacts, commitment of resources, short-term use of the environment and mitigation measures.

  17. Enrichment Zoning Options for the Small Nuclear Rocket Engine (SNRE)

    SciTech Connect (OSTI)

    Bruce G. Schnitzler; Stanley K. Borowski

    2010-07-01T23:59:59.000Z

    Advancement of U.S. scientific, security, and economic interests through a robust space exploration program requires high performance propulsion systems to support a variety of robotic and crewed missions beyond low Earth orbit. In NASAs recent Mars Design Reference Architecture (DRA) 5.0 study (NASA-SP-2009-566, July 2009), nuclear thermal propulsion (NTP) was again selected over chemical propulsion as the preferred in-space transportation system option because of its high thrust and high specific impulse (-900 s) capability, increased tolerance to payload mass growth and architecture changes, and lower total initial mass in low Earth orbit. An extensive nuclear thermal rocket technology development effort was conducted from 1955-1973 under the Rover/NERVA Program. The Small Nuclear Rocket Engine (SNRE) was the last engine design studied by the Los Alamos National Laboratory during the program. At the time, this engine was a state-of-the-art design incorporating lessons learned from the very successful technology development program. Past activities at the NASA Glenn Research Center have included development of highly detailed MCNP Monte Carlo transport models of the SNRE and other small engine designs. Preliminary core configurations typically employ fuel elements with fixed fuel composition and fissile material enrichment. Uniform fuel loadings result in undesirable radial power and temperature profiles in the engines. Engine performance can be improved by some combination of propellant flow control at the fuel element level and by varying the fuel composition. Enrichment zoning at the fuel element level with lower enrichments in the higher power elements at the core center and on the core periphery is particularly effective. Power flattening by enrichment zoning typically results in more uniform propellant exit temperatures and improved engine performance. For the SNRE, element enrichment zoning provided very flat radial power profiles with 551 of the 564 fuel elements within 1% of the average element power. Results for this and alternate enrichment zoning options for the SNRE are compared.

  18. Propulsion mechanisms in a helicon plasma thruster

    E-Print Network [OSTI]

    Sinenian, Nareg

    2008-01-01T23:59:59.000Z

    Electric thrusters offer an attractive option for various in-space propulsion tasks due to their high thrust efficiencies. The performance characteristics of a compact electric thruster utilizing a helicon plasma source ...

  19. The U.S. Nuclear Regulatory Commission Thermal-Hydraulic Research Program: Maintaining expertise in a changing environment

    SciTech Connect (OSTI)

    Sheron, B.W.; Shotkin, L.M.; Baratta, A.J.

    1993-04-01T23:59:59.000Z

    Throughout the 1970s and early 1980s, the U.S. Nuclear Regulatory Commission`s (NRC`s) thermal-hydraulic research program enjoyed ample funding, sponsored extensive experimental and analytical development programs, and attracted worldwide expertise. With the completion of the major experimental programs and with the promulgation of the revised emergency core-cooling system rule, both the funding and prominence of thermal-hydraulic research at the NRC have declined in recent years. This has led justifiably to the concern by some that the program may no longer have the minimal elements needed to maintain both expertise and world-class status. The purpose of this article is to describe the NRC`s current thermal-hydraulic research program and to show how this program ensures maintenance of a viable, robust research effort and retention of needed expertise and international leadership.

  20. Enterprise SRS: Leveraging Ongoing Operations To Advance Nuclear Fuel Cycles Research And Development Programs

    SciTech Connect (OSTI)

    Murray, Alice M.; Marra, John E.; Wilmarth, William R.; Mcguire, Patrick W.; Wheeler, Vickie B.

    2013-07-03T23:59:59.000Z

    The Savannah River Site (SRS) is repurposing its vast array of assets to solve future national issues regarding environmental stewardship, national security, and clean energy. The vehicle for this transformation is Enterprise SRS which presents a new, radical view of SRS as a united endeavor for ''all things nuclear'' as opposed to a group of distinct and separate entities with individual missions and organizations. Key among the Enterprise SRS strategic initiatives is the integration of research into facilities in conjunction with on-going missions to provide researchers from other national laboratories, academic institutions, and commercial entities the opportunity to demonstrate their technologies in a relevant environment and scale prior to deployment. To manage that integration of research demonstrations into site facilities, The Department of Energy, Savannah River Operations Office, Savannah River Nuclear Solutions, the Savannah River National Laboratory (SRNL) have established a center for applied nuclear materials processing and engineering research (hereafter referred to as the Center). The key proposition of this initiative is to bridge the gap between promising transformational nuclear fuel cycle processing discoveries and large commercial-scale-technology deployment by leveraging SRS assets as facilities for those critical engineering-scale demonstrations necessary to assure the successful deployment of new technologies. The Center will coordinate the demonstration of R&D technologies and serve as the interface between the engineering-scale demonstration and the R&D programs, essentially providing cradle-to-grave support to the research team during the demonstration. While the initial focus of the Center will be on the effective use of SRS assets for these demonstrations, the Center also will work with research teams to identify opportunities to perform research demonstrations at other facilities. Unique to this approach is the fact that these SRS assets will continue to accomplish DOE's critical nuclear material missions (e.g., processing in H-Canyon and plutonium storage in K-Area). Thus, the demonstration can be accomplished by leveraging the incremental cost of performing demonstrations without needing to cover the full operational cost of the facility. Current Center activities have been focused on integrating advanced safeguards monitoring technologies demonstrations into the SRS H-Canyon and advanced location technologies demonstrations into K-Area Materials Storage. These demonstrations are providing valuable information to researchers and customers as well as providing the Center with an improved protocol for demonstration management that can be exercised across the entire SRS (as well as to offsite venues) so that future demonstrations can be done more efficiently and provide an opportunity to utilize these unique assets for multiple purposes involving national laboratories, academia, and commercial entities. Key among the envisioned future demonstrations is the use of H-Canyon to demonstrate new nuclear materials separations technologies critical for advancing the mission needs DOE-Nuclear Energy (DOE-NE) to advance the research for next generation fuel cycle technologies. The concept is to install processing equipment on frames. The frames are then positioned into an H-Canyon cell and testing in a relevant radiological environment involving prototypic radioactive materials can be performed.

  1. Spent Nuclear Fuel Project document control and Records Management Program Description

    SciTech Connect (OSTI)

    MARTIN, B.M.

    2000-05-18T23:59:59.000Z

    The Spent Nuclear Fuel (SNF) Project document control and records management program, as defined within this document, is based on a broad spectrum of regulatory requirements, Department of Energy (DOE) and Project Hanford and SNF Project-specific direction and guidance. The SNF Project Execution Plan, HNF-3552, requires the control of documents and management of records under the auspices of configuration control, conduct of operations, training, quality assurance, work control, records management, data management, engineering and design control, operational readiness review, and project management and turnover. Implementation of the controls, systems, and processes necessary to ensure compliance with applicable requirements is facilitated through plans, directives, and procedures within the Project Hanford Management System (PHMS) and the SNF Project internal technical and administrative procedures systems. The documents cited within this document are those which directly establish or define the SNF Project document control and records management program. There are many peripheral documents that establish requirements and provide direction pertinent to managing specific types of documents that, for the sake of brevity and clarity, are not cited within this document.

  2. Transactions of the fourth symposium on space nuclear power systems

    SciTech Connect (OSTI)

    El-Genk, M.S.; Hoover, M.D. (eds.)

    1987-01-01T23:59:59.000Z

    This paper contains the presented papers at the fourth symposium on space nuclear power systems. Topics of these papers include: space nuclear missions and applications, reactors and shielding, nuclear electric and nuclear propulsion, refractory alloys and high-temperature materials, instrumentation and control, energy conversion and storage, space nuclear fuels, thermal management, nuclear safety, simulation and modeling, and multimegawatt system concepts. (LSP)

  3. Transactions of the fifth symposium on space nuclear power systems

    SciTech Connect (OSTI)

    El-Genk, M.S.; Hoover, M.D. (eds.)

    1988-01-01T23:59:59.000Z

    This paper contains the presented papers at the fourth symposium on space nuclear power systems. Topics of these paper include: space nuclear missions and applications, reactors and shielding, nuclear electric and nuclear propulsion, high-temperature materials, instrumentation and control, energy conversion and storage, space nuclear fuels, thermal management, nuclear safety, simulation and modeling, and multimegawatt system concepts. (LSP)

  4. Research, development and demonstration of nickel-zinc batteries for electric vehicle propulsion. Annual report, 1979

    SciTech Connect (OSTI)

    Not Available

    1980-06-01T23:59:59.000Z

    Activities in a program to develop a Ni/Zn battery for electric vehicle propulsion are reported. Aspects discussed include battery design and development, nickel cathode study, and basic electrochemistry. A number of engineering drawings are supplied. 61 figures, 11 tables. (RWR)

  5. Nuclear Medicine Program progress report for quarter ending September 30, 1991

    SciTech Connect (OSTI)

    Knapp, F.F. Jr.; Ambrose, K.R.; Callahan, A.P.; McPherson, D.W.; Mirzadeh, S.; Srivastava, P.C.; Hasan, A.; Lambert, C.R.; Lambert, S.J.; Rice, D.E.

    1992-02-01T23:59:59.000Z

    Rat tissue distribution properties of IQNP,'' a new radioiodinated cholinergic-muscarinic receptor antagonist, are described. IQNP is the acronym for 1-azabicyclo(2.2.2)oct-3-yl {alpha}-hydroxy-{alpha}-phenyl-{alpha}(1-iodo-1-propen-3-yl) acetate, which is an analogue of the QNB muscarinic antagonist in which the p-iodophenyl moiety has been replaced with the 1-iodo-1-propen-3-yl moiety. The radioiodinated IQNP analogue is easier to prepare in much higher yields than QNB and is thus a candidate for the evaluation of muscarinic receptors by external imaging techniques. Studies in rats demonstrated that IQNP shows high uptake in those cerebral regions rich in muscarinic receptors QNB-treatment of rats either 1 h before (pre) or 2 h after (post) administration of radioiodinated IQNP resulted in significant displacement or blocking of cerebral specific IQNP uptake (% dose/gm) in the cortex and striatum. These studies demonstrate that IQNP has specificity for the cholinergic-muscarinic receptor and is a good candidate for further studies. Also during this period, several agents developed in the ORNL Nuclear Medicine Program were supplied to Medical Cooperative Programs for collaborative studies including the iodine-125-labeled BMIPP and DMIPP fatty acid analogues and the IPM antibody labeling agent. Tin-117m and gold-199 were produced in the ORNL High Flux Isotope Reactor (HFIR) and supplied to the OHER-supported program in the Medical Department at Brookhaven National Laboratory to aid in their research until the re-start of the High Flux Brookhaven Reactor.

  6. Nuclear Medicine Program progress report for quarter ending September 30, 1991

    SciTech Connect (OSTI)

    Knapp, F.F. Jr.; Ambrose, K.R.; Callahan, A.P.; McPherson, D.W.; Mirzadeh, S.; Srivastava, P.C.; Hasan, A.; Lambert, C.R.; Lambert, S.J.; Rice, D.E.

    1992-02-01T23:59:59.000Z

    Rat tissue distribution properties of ``IQNP,`` a new radioiodinated cholinergic-muscarinic receptor antagonist, are described. IQNP is the acronym for 1-azabicyclo[2.2.2]oct-3-yl {alpha}-hydroxy-{alpha}-phenyl-{alpha}(1-iodo-1-propen-3-yl) acetate, which is an analogue of the QNB muscarinic antagonist in which the p-iodophenyl moiety has been replaced with the 1-iodo-1-propen-3-yl moiety. The radioiodinated IQNP analogue is easier to prepare in much higher yields than QNB and is thus a candidate for the evaluation of muscarinic receptors by external imaging techniques. Studies in rats demonstrated that IQNP shows high uptake in those cerebral regions rich in muscarinic receptors QNB-treatment of rats either 1 h before (pre) or 2 h after (post) administration of radioiodinated IQNP resulted in significant displacement or blocking of cerebral specific IQNP uptake (% dose/gm) in the cortex and striatum. These studies demonstrate that IQNP has specificity for the cholinergic-muscarinic receptor and is a good candidate for further studies. Also during this period, several agents developed in the ORNL Nuclear Medicine Program were supplied to Medical Cooperative Programs for collaborative studies including the iodine-125-labeled BMIPP and DMIPP fatty acid analogues and the IPM antibody labeling agent. Tin-117m and gold-199 were produced in the ORNL High Flux Isotope Reactor (HFIR) and supplied to the OHER-supported program in the Medical Department at Brookhaven National Laboratory to aid in their research until the re-start of the High Flux Brookhaven Reactor.

  7. 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.

  8. PAVAN: an atmospheric-dispersion program for evaluating design-basis accidental releases of radioactive materials from nuclear power stations

    SciTech Connect (OSTI)

    Bander, T.J.

    1982-11-01T23:59:59.000Z

    This report provides a user's guide for the NRC computer program, PAVAN, which is a program used by the US Nuclear Regulatory Commission to estimate downwind ground-level air concentrations for potential accidental releases of radioactive material from nuclear facilities. Such an assessment is required by 10 CFR Part 100 and 10 CFR Part 50. The program implements the guidance provided in Regulatory Guide 1.145, Atmospheric Dispersion Models for Potential Accident Consequence Assessments at Nuclear Power Plants. Using joint frequency distributions of wind direction and wind speed by atmospheric stability, the program provides relative air concentration (X/Q) values as functions of direction for various time periods at the exclusion area boundary (EAB) and the outer boundary of the low population zone (LPZ). Calculations of X/Q values can be made for assumed ground-level releases (e.g., through building penetrations and vents) or elevated releases from free-standing stacks. Various options may be selected by the user. They can account for variation in the location of release points, additional plume dispersion due to building wakes, plume meander under low wind speed conditions, and adjustments to consider non-straight trajectories. It computes an effective plume height using the physical release height which can be reduced by inputted terrain features. It cannot handle multiple emission sources. A description of the main program and all subroutines is provided. Also included as appendices are a complete listing of the program and two test cases with the required data inputs and the resulting program outputs.

  9. Spent nuclear fuels project: FY 1995 multi-year program plan, WBS {number_sign}1.4

    SciTech Connect (OSTI)

    Denning, J.L.

    1994-09-01T23:59:59.000Z

    The mission of the Spent Nuclear Fuel (SNF) program is to safely, reliably, and efficiently manage, condition, transport, and store Department of Energy (DOE)-owned SNF, so that it meets acceptance criteria for disposal in a permanent repository. The Hanford Site Spent Nuclear Fuel strategic plan for accomplishing the project mission is: Establish near-term safe storage in the 105-K Basins; Complete national Environmental Policy Act (NEPA) process to obtain a decision on how and where spent nuclear fuel will be managed on the site; Define and establish alternative interim storage on site or transport off site to support implementation of the NEPA decision; and Define and establish a waste package qualified for final disposition. This report contains descriptions of the following: Work Breakdown Structure; WBS Dictionary; Responsibility Assignment Matrix; Program Logic Diagrams; Program Master Baseline Schedule; Program Performance Baseline Schedule; Milestone List; Milestone Description Sheets; Cost Baseline Summary by Year; Basis of Estimate; Waste Type Data; Planned Staffing; and Fiscal Year Work Plan.

  10. General-purpose heat source project and space nuclear safety and fuels program. Progress reportt, January 1980

    SciTech Connect (OSTI)

    Maraman, W.J. (comp.)

    1980-04-01T23:59:59.000Z

    This formal monthly report covers the studies related to the use of /sup 238/PuO/sub 2/ in radioisotopic power systems carried out for the Advanced Nuclear Systems and Projects Division of the Los Alamos Scientific Laboratory. The two programs involved are the general-purpose heat source development and space nuclear safety and fuels. Most of the studies discussed here are of a continuing nature. Results and conclusions described may change as the work continues. Published reference to the results cited in this report should not be made without the explicit permission of the person in charge of the work.

  11. New Resolved Resonance Region Evaluation for 63Cu and 65Cu for Nuclear Criticality Safety Program

    SciTech Connect (OSTI)

    Sobes, Vladimir [ORNL] [ORNL; Leal, Luiz C [ORNL] [ORNL; Guber, Klaus H [ORNL] [ORNL; Forget, Benoit [Massachusetts Institute of Technology (MIT)] [Massachusetts Institute of Technology (MIT); Kopecky, S. [EC-JRC-IRMM, Geel, Belgium] [EC-JRC-IRMM, Geel, Belgium; Schillebeeckx, P. [EC-JRC-IRMM, Geel, Belgium] [EC-JRC-IRMM, Geel, Belgium; Siegler, P. [EC-JRC-IRMM, Geel, Belgium] [EC-JRC-IRMM, Geel, Belgium

    2014-01-01T23:59:59.000Z

    A new resolved resonance region evaluation of 63Cu and 65Cu was done in the energy region from 10-5 eV to 99.5 keV. The R-Matrix SAMMY method using the Reich-Moore approximation was used to create a new set of consistent resonance parameters. The new evaluation was based on three experimental transmission data sets; two measured at ORELA and one from MITR, and two radiative capture experimental data sets from GELINA. A total of 141 new resonances were identied for 63Cu and 117 for 65Cu. The corresponding set of external resonances for each isotope was based on the identied resonances above 99.5 keV from the ORELA transmission data. The negative external levels (bound levels) were determined to match the dierential thermal cross section measured at the MITR. Double dierential elastic scattering cross sections were calculated from the new set of resonance parameters. Benchmarking calculations were carried out on a set of ICSBEP benchmarks. This work is in support of the DOE Nuclear Criticality Safety Program.

  12. Viability of an expanded United States nuclear power program and its effects on energy markets

    E-Print Network [OSTI]

    Khan, Tanzeer S

    2006-01-01T23:59:59.000Z

    The four biggest energy sources in the United States are coal, crude oil, natural gas, and nuclear power. While coal and nuclear power are produced domestically, more than 70% of crude oil and 20% of natural gas is imported. ...

  13. Self-Reliability and Motivation in a Nuclear Security Culture Enhancement Program

    SciTech Connect (OSTI)

    Crawford, Cary E.; de Boer, Gloria; De Castro, Kara; Landers, John; Rogers, Erin

    2010-10-01T23:59:59.000Z

    The threat of nuclear terrorism has become a global concern. Many countries continue to make efforts to strengthen nuclear security by enhancing systems of nuclear material protection, control, and accounting (MPC&A). Though MPC&A systems can significantly upgrade nuclear security, they do not eliminate the human factor. Gen. Eugene Habiger, a former Assistant Secretary for Safeguards and Security at the U.S. Department of Energys (DOE) nuclear-weapons complex and a former commander of U.S. strategic nuclear forces, has observed that good security is 20% equipment and 80% people.1 Although eliminating the human factor is not possible, accounting for and mitigating the risk of the insider threat is an essential element in establishing an effective nuclear security culture. This paper will consider the organizational role in mitigating the risk associated with the malicious insider through monitoring and enhancing human reliability and motivation as well as enhancing the nuclear security culture.

  14. Power balance in a helicon plasma source for space propulsion

    E-Print Network [OSTI]

    White, Daniel B., Jr

    2008-01-01T23:59:59.000Z

    Electric propulsion systems provide an attractive option for various spacecraft propulsion applications due to their high specific impulse. The power balance of an electric thruster based on a helicon plasma source is ...

  15. Massachusetts Beryllium Screening Program for Former Workers of Wyman-Gordon, Norton Abrasives, and MIT/Nuclear Metals

    SciTech Connect (OSTI)

    Pepper, L.D.

    2008-05-21T23:59:59.000Z

    The overall objective of this project was to provide medical screening to former workers of Wyman-Gordon Company, Norton Abrasives, and MIT/Nuclear Metals (NMI) in order to prevent and minimize the health impact of diseases caused by site related workplace exposures to beryllium. The program was developed in response to a request by the U.S. Department of Energy (DOE) that had been authorized by Congress in Section 3162 of the 1993 Defense Authorization Act, urging the DOE to ??carry out a program for the identification and ongoing evaluation of current and former DOE employees who are subjected to significant health risks during such employment." This program, funded by the DOE, was an amendment to the medical surveillance program for former DOE workers at the Nevada Test Site (NTS). This program??s scope included workers who had worked for organizations that provided beryllium products or materials to the DOE as part of their nuclear weapons program. These organizations have been identified as Beryllium Vendors.

  16. RISKIND: A computer program for calculating radiological consequences and health risks from transportation of spent nuclear fuel

    SciTech Connect (OSTI)

    Yuan, Y.C. [Square Y, Orchard Park, NY (United States); Chen, S.Y.; LePoire, D.J. [Argonne National Lab., IL (United States). Environmental Assessment and Information Sciences Div.; Rothman, R. [USDOE Idaho Field Office, Idaho Falls, ID (United States)

    1993-02-01T23:59:59.000Z

    This report presents the technical details of RISIUND, a computer code designed to estimate potential radiological consequences and health risks to individuals and the collective population from exposures associated with the transportation of spent nuclear fuel. RISKIND is a user-friendly, semiinteractive program that can be run on an IBM or equivalent personal computer. The program language is FORTRAN-77. Several models are included in RISKIND that have been tailored to calculate the exposure to individuals under various incident-free and accident conditions. The incidentfree models assess exposures from both gamma and neutron radiation and can account for different cask designs. The accident models include accidental release, atmospheric transport, and the environmental pathways of radionuclides from spent fuels; these models also assess health risks to individuals and the collective population. The models are supported by databases that are specific to spent nuclear fuels and include a radionudide inventory and dose conversion factors.

  17. Propulsion in a viscoelastic fluid Eric Laugaa

    E-Print Network [OSTI]

    Lauga, Eric

    and a healthy respiratory system.8 Cilia are short flagella which produce fluid motion by means mechanisms and propulsion.9 In the upper respiratory tract, cilia are located in a thin layer of low influenced by viscoelastic stresses. Relevant examples include the ciliary transport of respiratory airway

  18. Nuclear facility decommissioning and site remedial actions: A selected bibliography, Volume 13: Part 1, Main text. Environmental Restoration Program

    SciTech Connect (OSTI)

    Goins, L.F.; Webb, J.R.; Cravens, C.D.; Mallory, P.K.

    1992-09-01T23:59:59.000Z

    This publication contains 1035 abstracted references on environmental restoration, nuclear facility decommissioning, uranium mill tailings management, and site remedial actions. These citations constitute the thirteenth in a series of reports prepared annually for the US Department of Energy (DOE) Environmental Restoration programs. Citations to foreign and domestic literature of all types. There are 13 major sections of the publication, including: (1) DOE Decontamination and Decommissioning Program; (2) Nuclear Facilities Decommissioning; (3) DOE Formerly Utilized Sites Remedial Action Program; (4) DOE Uranium Mill Tailings Remedial Action Project; (5) Uranium Mill Tailings Management; (6) DOE Environmental Restoration Program; (7) DOE Site-Specific Remedial Actions; (8) Contaminated Site Restoration; (9) Remediation of Contaminated Soil and Groundwater; (10) Environmental Data Measurements, Management, and Evaluation; (11) Remedial Action Assessment and Decision-Making; (12) Technology Development and Evaluation; and (13) Environmental and Waste Management Issues. Bibliographic references are arranged in nine subject categories by geographic location and then alphabetically by first author, corporate affiliation, or publication title. Indexes are provided for author, corporate affiliation, title word, publication description, geographic location, subject category, and key word.

  19. Enterprise SRS: leveraging ongoing operations to advance nuclear fuel cycles research and development programs

    SciTech Connect (OSTI)

    Murray, A.M.; Marra, J.E.; Wilmarth, W.R. [Savannah River National Laboratory, Aiken, SC 29808 (United States); McGuire, P.W.; Wheeler, V.B. [Department of Energy-Savannah River Operations Office, Aiken SC 29808 (United States)

    2013-07-01T23:59:59.000Z

    The Savannah River Site (SRS) is re-purposing its vast array of assets (including H Canyon - a nuclear chemical separation plant) to solve issues regarding advanced nuclear fuel cycle technologies, nuclear materials processing, packaging, storage and disposition. The vehicle for this transformation is Enterprise SRS which presents a new, radical view of SRS as a united endeavor for 'all things nuclear' as opposed to a group of distinct and separate entities with individual missions and organizations. Key among the Enterprise SRS strategic initiatives is the integration of research into SRS facilities but also in other facilities in conjunction with on-going missions to provide researchers from other national laboratories, academic institutions, and commercial entities the opportunity to demonstrate their technologies in a relevant environment and scale prior to deployment. To manage that integration of research demonstrations into site facilities, a center for applied nuclear materials processing and engineering research has been established in SRS.

  20. Space nuclear-power reactor design based on combined neutronic and thermal-fluid analyses

    SciTech Connect (OSTI)

    Koenig, D.R.; Gido, R.G.; Brandon, D.I.

    1985-01-01T23:59:59.000Z

    The design and performance analysis of a space nuclear-power system requires sophisticated analytical capabilities such as those developed during the nuclear rocket propulsion (Rover) program. In particular, optimizing the size of a space nuclear reactor for a given power level requires satisfying the conflicting requirements of nuclear criticality and heat removal. The optimization involves the determination of the coolant void (volume) fraction for which the reactor diameter is a minimum and temperature and structural limits are satisfied. A minimum exists because the critical diameter increases with increasing void fraction, whereas the reactor diameter needed to remove a specified power decreases with void fraction. The purpose of this presentation is to describe and demonstrate our analytical capability for the determination of minimum reactor size. The analysis is based on combining neutronic criticality calculations with OPTION-code thermal-fluid calculations.

  1. Research, development, and demonstration of nickel-iron batteries for electric vehicle propulsion. Annual report, 1980

    SciTech Connect (OSTI)

    Not Available

    1981-03-01T23:59:59.000Z

    The objective of the Eagle-Picher nickel-iron battery program is to develop a nickel-iron battery for use in the propulsion of electric and electric-hybrid vehicles. To date, the program has concentrated on the characterization, fabrication and testing of the required electrodes, the fabrication and testing of full-scale cells, and finally, the fabrication and testing of full-scale (270 AH) six (6) volt modules. Electrodes of the final configuration have now exceeded 1880 cycles and are showing minimal capacity decline. Full-scale cells have presently exceeded 600 cycles and are tracking the individual electrode tests almost identically. Six volt module tests have exceeded 500 cycles, with a specific energy of 48 Wh/kg. Results to date indicate the nickel-iron battery is beginning to demonstrate the performance required for electric vehicle propulsion.

  2. Dedicated Laboratory Setup for CO{sub 2} TEA Laser Propulsion Experiments at Rensselaer Polytechnic Institute

    SciTech Connect (OSTI)

    Salvador, Israel I.; Kenoyer, David; Myrabo, Leik N.; Notaro, Samuel [Department of Mechanical, Aerospace, and Nuclear Engineering, Rensselaer Polytechnic Institute, Troy, NY, 12180 (United States)

    2010-10-08T23:59:59.000Z

    Laser propulsion research progress has traditionally been hindered by the scarcity of photon sources with desirable characteristics, as well as integrated specialized flow facilities in a dedicated laboratory environment. For TEA CO{sub 2} lasers, the minimal requirements are time-average powers of >100 W), and pulse energies of >10 J pulses with short duration (e.g., 0.1 to 1 {mu}s); furthermore, for the advanced pulsejet engines of interest here, the laser system must simulate pulse repetition frequencies of 1-10 kilohertz or more, at least for two (carefully sequenced) pulses. A well-equipped laser propulsion laboratory should have an arsenal of sensor and diagnostics tools (such as load cells, thrust stands, moment balances, pressure and heat transfer gages), Tesla-level electromagnet and permanent magnets, flow simulation facilities, and high-speed visualization systems, in addition to other related equipment, such as optics and gas supply systems. In this paper we introduce a cutting-edge Laser Propulsion Laboratory created at Rensselaer Polytechnic Institute, one of the very few in the world to be uniquely set up for beamed energy propulsion (BEP) experiments. The present BEP research program is described, along with the envisioned research strategy that will exploit current and expanded facilities in the near future.

  3. Safety research programs sponsored by Office of Nuclear Regulatory Research: Quarterly progress report, July 1-September 30, 1986

    SciTech Connect (OSTI)

    Bari, R.A.; Bezler, P.; Boccio, J.L.; Ginsberg, T.; Greene, G.A.; Guppy, J.G.; Hall, R.E.; Hofmayer, C.H.; Khatib-Rahbar, H.; Luckas, W.J. Jr.

    1987-03-01T23:59:59.000Z

    This progress report will describe current activities and technical progress in the programs at Brookhaven National Laboratory sponsored by the Division of Accident Evaluation, Division of Engineering Technology, and Division of Risk Analysis and Operations of the US Nuclear Regulatory Commission, Office of Nuclear Regulatory Research. The projects reported are the following: High Temperature Reactor Research, SSC code improvements, Thermal-Hydraulic Reactor Safety Experiments, Thermodynamic Core-Concrete Interaction Experiments and Analysis, Plant Analyzer, Code Assessment and Application, Code Maintenance (RAMONA-3B), MELCOR Verification and Benchmarking, Source Term Code Package Verification and Benchmarking, Uncertainty Analysis of the Source Term; Stress Corrosion Cracking of PWR Steam Generator Tubing, Soil-Structure Interaction Evaluation and Structural Benchmarks, Identification of Age Related Failure Modes; Application of HRA/PRA Results to Support Resolution of Generic Safety Issues Involving Human Performance, Protective Action Decisionmaking, Rebaseling of Risk for Zion, Containment Performance Design Objective, and Operational Safety Reliability Research.

  4. Stability and Nukes: China's Domestic Concerns over North Korea's Nuclear Program

    E-Print Network [OSTI]

    Xu, Jun

    2014-05-31T23:59:59.000Z

    While the bilateral friendship between China and North Korea was solidified and endured during the Korean war, Beijing's ties to Pyongyang have weakened considerably during the nuclear crisis on the Korean Peninsula, which ...

  5. SERAPHIM: A propulsion technology for fast trains

    SciTech Connect (OSTI)

    Kelly, B.; Turman, B.; Marder, B.; Rohwein, G.; Aeschliman, D.; Cowan, B.

    1995-06-01T23:59:59.000Z

    The Segmented Rail Phased Induction Motor (SERAPHIM) is a compact, pulsed linear induction motor (LIM) offering a unique capability for very high speed train propulsion. It uses technology developed for the Sandia coilgun, an electromagnetic launcher designed to accelerate projectiles to several kilometers per second. Both aluminum cylinders and plates were accelerated to a kilometer per second (Mach 3) by passing through a sequence of coils which were energized at the appropriate time. Although this technology was developed for ultra-high velocity, it can be readily adapted to train propulsion for which, at sea level, the power required to overcome air resistance limits the operational speed to a more modest 300 mph. Here, the geometry is reversed. The coils are on the vehicle and the ``projectiles`` are fixed along the roadbed. SERAPHIM operates not by embedding flux in a conductor, but by excluding it. In this propulsion scheme, pairs of closely spaced coils on the vehicle straddle a segmented aluminum reaction rail. A high frequency current is switched on as a coil pair crosses an edge and remains off as they overtake the next segment. This induces surface currents which repel the coil. In essence, the pulsed coils push off segment edges because at the high frequency of operation, the flux has insufficient time to penetrate. In contrast to conventional LIMs, the performance actually improves with velocity, even for a minimal motor consisting of a single coil pair reacting with a single plate. This paper will present results of proof-of-principle tests, electromagnetic computer simulations, and systems analysis. It is concluded that this new linear induction motor can be implemented using existing technology and is a promising alternative propulsion method for very high speed rail transportation.

  6. The NASA CSTI High Capacity Power Program

    SciTech Connect (OSTI)

    Winter, J.M.

    1994-09-01T23:59:59.000Z

    The SP-100 program was established in 1983 by DOD, DOE, and NASA as a joint program to develop the technology necessary for space nuclear power systems for military and civil applications. During 1986 and 1987, the NASA Advanced Technology Program was responsible for maintaining the momentum of promising technology advancement efforts started during Phase I of SP-100 and to strengthen, in key areas, the chances for successful development and growth capability of space nuclear reactor power systems for future space applications. In 1988, the NASA Advanced Technology Program was incorporated into NASA`s new Civil Space Technology Initiative (CSTI). The CSTI program was established to provide the foundation for technology development in automation and robotics, information, propulsion, and power. The CSTI High Capacity Power Program builds on the technology efforts of the SP-100 program, incorporates the previous NASA advanced technology project, and provides a bridge to the NASA exploration technology programs. The elements of CSTI high capacity power development include conversion systems - Stirling and thermoelectric, thermal management, power management, system diagnostics, and environmental interactions. Technology advancement in all areas, including materials, is required to provide the growth capability, high reliability and 7 to 10 years lifetime demanded for future space nuclear power systems. The overall program will develop and demonstrate the technology base required to provide a wide range of modular power systems while minimizing the impact of day/night operation as well as attitudes and distance from the Sun. Significant accomplishments in all of the program elements will be discussed, along with revised goals and project timelines recently developed.

  7. NWTS program criteria for mined geologic disposal of nuclear waste: repository performance and development criteria. Public draft

    SciTech Connect (OSTI)

    none,

    1982-07-01T23:59:59.000Z

    This document, DOE/NWTS-33(3) is one of a series of documents to establish the National Waste Terminal Storage (NWTS) program criteria for mined geologic disposal of high-level radioactive waste. For both repository performance and repository development it delineates the criteria for design performance, radiological safety, mining safety, long-term containment and isolation, operations, and decommissioning. The US Department of Energy will use these criteria to guide the development of repositories to assist in achieving performance and will reevaluate their use when the US Nuclear Regulatory Commission issues radioactive waste repository rules.

  8. Idaho Nuclear Technology and Engineering Center Low-Activity Waste Process Technology Program FY-98 Status Report

    SciTech Connect (OSTI)

    Herbst, Alan Keith; Mc Cray, John Alan; Rogers, Adam Zachary; Simmons, R. F.; Palethorpe, S. J.

    1999-03-01T23:59:59.000Z

    The Low-Activity Waste Process Technology Program at the Idaho Nuclear Technology and Engineering Center (INTEC) anticipates that large volumes of low-level/low-activity wastes will need to be grouted prior to near-surface disposal. During fiscal year 1998, three grout formulations were studied for low-activity wastes derived from INTEC liquid sodium-bearing waste. Compressive strength and leach results are presented for phosphate bonding cement, acidic grout, and alkaline grout formulations. In an additional study, grout formulations are recommended for stabilization of the INTEC underground storage tank residual heels.

  9. Idaho Nuclear Technology and Engineering Center Low-Activity Waste Process Technology Program, FY-98 Status Report

    SciTech Connect (OSTI)

    Herbst, A.K.; Rogers, A.Z.; McCray, J.A.; Simmons, R.F.; Palethorpe, S.J.

    1999-03-01T23:59:59.000Z

    The Low-Activity Waste Process Technology Program at the Idaho Nuclear Technology and Engineering Center (INTEC) anticipates that large volumes of low-level/low-activity wastes will need to be grouted prior to near-surface disposal. During fiscal year 1998, three grout formulations were studied for low-activity wastes derived from INTEC liquid sodium-bearing waste. Compressive strength and leach results are presented for phosphate bonding cement, acidic grout, and alkaline grout formulations. In an additional study, grout formulations are recommended for stabilization of the INTEC underground storage tank residual heels.

  10. Idaho Nuclear Technology and Engineering Center Low-Activity Waste Process Technology Program FY-2000 Status Report

    SciTech Connect (OSTI)

    Herbst, Alan Keith; Mc Cray, John Alan; Kirkham, Robert John; Pao, Jenn Hai; Argyle, Mark Don; Lauerhass, Lance; Bendixsen, Carl Lee; Hinckley, Steve Harold

    2000-11-01T23:59:59.000Z

    The Low-Activity Waste Process Technology Program anticipated that grouting will be used for disposal of low-level and transuranic wastes generated at the Idaho Nuclear Technology Engineering Center (INTEC). During fiscal year 2000, grout formulations were studied for transuranic waste derived from INTEC liquid sodium-bearing waste and for projected newly generated low-level liquid waste. Additional studies were completed using silica gel and other absorbents to solidify sodium-bearing wastes. A feasibility study and conceptual design were completed for the construction of a grout pilot plant for simulated wastes and demonstration facility for actual wastes.

  11. Idaho Nuclear Technology and Engineering Center Low-Activity Waste Process Technology Program FY-2000 Status Report

    SciTech Connect (OSTI)

    Herbst, A.K.; McCray, J.A.; Kirkham, R.J.; Pao, J.; Argyle, M.D.; Lauerhass, L.; Bendixsen, C.L.; Hinckley, S.H.

    2000-10-31T23:59:59.000Z

    The Low-Activity Waste Process Technology Program anticipated that grouting will be used for disposal of low-level and transuranic wastes generated at the Idaho Nuclear Technology Engineering Center (INTEC). During fiscal year 2000, grout formulations were studied for transuranic waste derived from INTEC liquid sodium-bearing waste and for projected newly generated low-level liquid waste. Additional studies were completed using silica gel and other absorbents to solidify sodium-bearing wastes. A feasibility study and conceptual design were completed for the construction of a grout pilot plant for simulated wastes and demonstration facility for actual wastes.

  12. Idaho Nuclear Technology and Engineering Center Low-Activity Waste Process Technology Program FY-99 Status Report

    SciTech Connect (OSTI)

    A. K. Herbst; J. A. McCray; R. J. Kirkham; J. Pao; S. H. Hinckley

    1999-09-30T23:59:59.000Z

    The Low-Activity Waste Process Technology Program at the Idaho Nuclear Technology and Engineering Center (INTEC) anticipates that large volumes of low-level/low-activity wastes will need to be grouted prior to near-surface disposal. During fiscal year 1999, grout formulations were studied for transuranic waste derived from INTEC liquid sodium-bearing waste and for projected newly generated low-level liquid waste. Additional studies were completed on radionuclide leaching, microbial degradation, waste neutralization, and a small mockup for grouting the INTEC underground storage tank residual heels.

  13. Idaho Nuclear Technology and Engineering Center Low-Activity Waste Process Technology Program FY-99 Status Report

    SciTech Connect (OSTI)

    Herbst, Alan Keith; Mc Cray, John Alan; Kirkham, Robert John; Pao, Jenn Hai; Hinckley, Steve Harold

    1999-10-01T23:59:59.000Z

    The Low-Activity Waste Process Technology Program at the Idaho Nuclear Technology and Engineering Center (INTEC) anticipates that large volumes of low-level/low-activity wastes will need to be grouted prior to near-surface disposal. During fiscal year 1999, grout formulations were studied for transuranic waste derived from INTEC liquid sodium-bearing waste and for projected newly generated low-level liquid waste. Additional studies were completed on radionuclide leaching, microbial degradation, waste neutralization, and a small mockup for grouting the INTEC underground storage tank residual heels.

  14. Nuclear Safety Research and Development...

    Energy Savers [EERE]

    Nuclear Safety Research and Development Proposal Review and Prioritization Process and Criteria Nuclear Safety Research and Development Program Office of Nuclear Safety Office of...

  15. Comparison of Space Propulsion Methods for a Manned Mission to Mars

    E-Print Network [OSTI]

    Guerra, A G C; Gil, P J S

    2015-01-01T23:59:59.000Z

    We undertake a comparison of the latest developments in propulsion technologies, for a manned mission to Mars. The main objective is to assess the possibility of reducing travel time keeping the mass at departure within bounds. For the sake of comparison we used representative systems of different state of the art or proposed technologies, from the chemical engine to the "Pure Electro-Magnetic Thrust" (PEMT) concept, using a nuclear engine proposed by Rubbia. A mission architecture is suggested, based on existing mission proposals to Mars, to estimate the mass budget that influences the performance of the propulsion system. The trajectory of the spacecraft is determined by a numerical integration of the equations of motion and a partial optimization procedure, for the interplanetary phase with continuous thrust, and by conics and instant manoeuvres in the regions of influence of the departure and arrival planets. Pareto curves of the duration of the mission and time of flight versus mass of mission are drawn....

  16. Simplest AB-Thermonuclear Space Propulsion and Electric Generator

    E-Print Network [OSTI]

    Alexander Bolonkin

    2007-01-19T23:59:59.000Z

    The author applies, develops and researches mini-sized Micro- AB Thermonuclear Reactors for space propulsion and space power systems. These small engines directly convert the high speed charged particles produced in the thermonuclear reactor into vehicle thrust or vehicle electricity with maximum efficiency. The simplest AB-thermonuclear propulsion offered allows spaceships to reach speeds of 20,000 50,000 km/s (1/6 of light speed) for fuel ratio 0.1 and produces a huge amount of useful electric energy. Offered propulsion system permits flight to any planet of our Solar system in short time and to the nearest non-Sun stars by E-being or intellectual robots during a single human life period. Key words: AB-propulsion, thermonuclear propulsion, space propulsion, thermonuclear power system.

  17. A nuclear physics program at the Rare Isotope Beams Accelerator Facility in Korea

    SciTech Connect (OSTI)

    Moon, Chang-Bum, E-mail: cbmoon@hoseo.edu [Hoseo University, Asan, Chung-Nam 336-795 (Korea, Republic of)] [Hoseo University, Asan, Chung-Nam 336-795 (Korea, Republic of)

    2014-04-15T23:59:59.000Z

    This paper outlines the new physics possibilities that fall within the field of nuclear structure and astrophysics based on experiments with radioactive ion beams at the future Rare Isotope Beams Accelerator facility in Korea. This ambitious multi-beam facility has both an Isotope Separation On Line (ISOL) and fragmentation capability to produce rare isotopes beams (RIBs) and will be capable of producing and accelerating beams of wide range mass of nuclides with energies of a few to hundreds MeV per nucleon. The large dynamic range of reaccelerated RIBs will allow the optimization in each nuclear reaction case with respect to cross section and channel opening. The low energy RIBs around Coulomb barrier offer nuclear reactions such as elastic resonance scatterings, one or two particle transfers, Coulomb multiple-excitations, fusion-evaporations, and direct capture reactions for the study of the very neutron-rich and proton-rich nuclides. In contrast, the high energy RIBs produced by in-flight fragmentation with reaccelerated ions from the ISOL enable to explore the study of neutron drip lines in intermediate mass regions. The proposed studies aim at investigating the exotic nuclei near and beyond the nucleon drip lines, and to explore how nuclear many-body systems change in such extreme regions by addressing the following topics: the evolution of shell structure in areas of extreme proton to neutron imbalance; the study of the weak interaction in exotic decay schemes such as beta-delayed two-neutron or two-proton emission; the change of isospin symmetry in isobaric mirror nuclei at the drip lines; two protons or two neutrons radioactivity beyond the drip lines; the role of the continuum states including resonant states above the particle-decay threshold in exotic nuclei; and the effects of nuclear reaction rates triggered by the unbound proton-rich nuclei on nuclear astrophysical processes.

  18. automotive propulsion system: Topics by E-print Network

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

    analysis; automotive control system. I. INTRODUCTION In reliability Zachmann, Gabriel 49 Mini-Micro Thrusters, LOX Hydrocarbon Propulsion, and Attitude Control...

  19. automotive propulsion systems: Topics by E-print Network

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

    analysis; automotive control system. I. INTRODUCTION In reliability Zachmann, Gabriel 49 Mini-Micro Thrusters, LOX Hydrocarbon Propulsion, and Attitude Control...

  20. advanced propulsion systems: Topics by E-print Network

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

    for the tail's motion. Index terms--Fish propulsion, underwater robot, fish design. I. INTRODUCTION LTHOUGH almost all marine vehicles use propellers Papadopoulos,...

  1. aircraft propulsion reactors: Topics by E-print Network

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

    to produce adequate thrust, reduce ... Dicara, Daniel L 2006-01-01 13 Simplest AB-Thermonuclear Space Propulsion and Electric Generator CERN Preprints Summary: The author...

  2. Enabling Green Energy and Propulsion Systems via Direct Noise...

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

    Umesh Paliath, GE Global Research; Joe Insley, Argonne National Laboratory Enabling Green Energy and Propulsion Systems via Direct Noise Computation PI Name: Umesh Paliath PI...

  3. National Nuclear Security Administration

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

    the safety, security and effectiveness of the nuclear deterrent without underground nuclear testing, consistent with the principles of the Stockpile Management Program...

  4. Nuclear Facility Maintenance Management Program Guide for Use with DOE O 433.1

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

    2001-09-05T23:59:59.000Z

    This Guide describes a maintenance management program that would be acceptable to DOE for meeting the requirements of DOE O 433.1. Canceled by DOE G 433.1-1A.

  5. Groundwater monitoring program plan and conceptual site model for the Al-Tuwaitha Nuclear Research Center in Iraq.

    SciTech Connect (OSTI)

    Copland, John Robin; Cochran, John Russell

    2013-07-01T23:59:59.000Z

    The Radiation Protection Center of the Iraqi Ministry of Environment is developing a groundwater monitoring program (GMP) for the Al-Tuwaitha Nuclear Research Center located near Baghdad, Iraq. The Al-Tuwaitha Nuclear Research Center was established in about 1960 and is currently being cleaned-up and decommissioned by Iraq's Ministry of Science and Technology. This Groundwater Monitoring Program Plan (GMPP) and Conceptual Site Model (CSM) support the Radiation Protection Center by providing:A CSM describing the hydrogeologic regime and contaminant issues,recommendations for future groundwater characterization activities, anddescriptions of the organizational elements of a groundwater monitoring program. The Conceptual Site Model identifies a number of potential sources of groundwater contamination at Al-Tuwaitha. The model also identifies two water-bearing zones (a shallow groundwater zone and a regional aquifer). The depth to the shallow groundwater zone varies from approximately 7 to 10 meters (m) across the facility. The shallow groundwater zone is composed of a layer of silty sand and fine sand that does not extend laterally across the entire facility. An approximately 4-m thick layer of clay underlies the shallow groundwater zone. The depth to the regional aquifer varies from approximately 14 to 17 m across the facility. The regional aquifer is composed of interfingering layers of silty sand, fine-grained sand, and medium-grained sand. Based on the limited analyses described in this report, there is no severe contamination of the groundwater at Al-Tuwaitha with radioactive constituents. However, significant data gaps exist and this plan recommends the installation of additional groundwater monitoring wells and conducting additional types of radiological and chemical analyses.

  6. The Gasdynamic Mirror Fusion Propulsion System -- Revisited

    SciTech Connect (OSTI)

    Kammash, Terry [Department of Nuclear Engineering and Radiological Sciences, University of Michigan, 2355 Bonisteel Blvd, Ann Arbor, MI 48109 (United States); Tang, Ricky [Department of Aerospace Engineering, University Michigan, 1320 Beal Ave, Ann Arbor, MI 48109 (United States)

    2005-02-06T23:59:59.000Z

    Many of the previous studies assessing the capability of the gasdynamic mirror (GDM) fusion propulsion system employed analyses that ignored the 'ambipolar' potential. This electrostatic potential arises as a result of the rapid escape of the electrons due to their small mass. As they escape, they leave behind an excess positive charge which manifests itself in an electric field that slows down the electrons while speeding up the ions until their respective axial diffusions are equalized. The indirect effect on the ions is that their confinement time is reduced relative to that of zero potential, and hence the plasma length must be increased to accommodate that change. But as they emerge from the thruster mirror - which serves as a magnetic nozzle - the ions acquire an added energy equal to that of the potential energy, and that in turn manifests itself in increased specific impulse and thrust. We assess the propulsive performance of the GDM thruster, based on the more rigorous theory, by applying it to a round trip Mars mission employing a continuous burn acceleration/deceleration type of trajectory. We find that the length of the device and travel time decrease with increasing plasma density, while the total vehicle mass reaches a minimum at a plasma density of 3 x 1016 cm-3. At such a density, and an initial DT ion temperature of 10 keV, a travel time of 60 days is found to be achievable at GDM propulsion parameters of about 200,000 seconds of specific impulse and approximately 47 kN of thrust.

  7. CMC intake ramp for hypersonic propulsion systems

    SciTech Connect (OSTI)

    Kochendoerfer, R.; Krenkel, W. [Institute of Structures and Design, Stuttgart, (Germany)

    1995-12-01T23:59:59.000Z

    An alternative technology to produce CMC structural components with lower costs and shorter manufacturing times has been developed at the DLR. The process is based on liquid silicon infiltration (LSI) into porous carbon/carbon resulting in a C/C-SiC material whereby the load carrying fibres are internally protected against oxidation by SiC. The material`s adequate strength levels and the high reproducibility of the state-of-the-art process now allows the realization of CMC components. Representing a very complex structure of high integrity, an intake ramp for a hypersonic propulsion system has been designed, manufactured and tested, which is described in this paper.

  8. Fusion Propulsion and Power for Future Flight

    SciTech Connect (OSTI)

    Froning, H.D. Jr.

    1996-02-01T23:59:59.000Z

    There are innovative magnetic and electric confinement fusion power and propulsion system designs with potential for: vacuum specific impulses of 1500-2000 seconds with rocket engine thrust/mass ratios of 5-10 g`s; environmentally favorable exhaust emissions if aneutronic fusion propellants can be used; a 2 to 3-fold reduction in the mass of hypersonic airliners and SSTO aerospace planes; a 10 to 20 fold reduction in Mars expedition mass and cost (if propellant from planetary atmospheres is used); and feasibility or in-feasibility of these systems could be confirmed with a modest applied research and exploratory development cost.

  9. Utilizing a Russian space nuclear reactor for a United States space mission: Systems integration issues

    SciTech Connect (OSTI)

    Reynolds, E.; Schaefer, E. [Johns Hopkins Univ., Laurel, MD (United States). Applied Physics Lab.; Polansky, G.; Lacy, J. [Phillips Lab., Albuquerque, NM (United States); Bocharov, A. [GDBMB, St. Petersburg (Russian Federation)

    1993-09-30T23:59:59.000Z

    The Nuclear Electric Propulsion Space Test Program (NEPSTP) has developed a cooperative relationship with several institutes of the former Soviet Union to evaluate Russian space hardware on a US spacecraft One component is the Topaz II Nuclear Power System; a built and flight qualified nuclear reactor that has yet to be tested in space. The access to the Topaz II reactor provides the NEPSTP with a rare opportunity; to conduct an early flight demonstration of nuclear electric propulsion at a relatively low cost. This opportunity, however, is not without challenges. Topaz II was designed to be compatible with Russian spacecraft and launch vehicles. It was manufactured and flight qualified by Russian techniques and standards and conforms to safety requirements of the former Soviet Union, not the United States. As it is desired to make minimal modifications to the Topaz II, integrating the reactor system with a United States spacecraft and launch vehicle presents an engineering challenge. This paper documents the lessons teamed regarding the integration of reactor based spacecraft and also some insight about integrating Russian hardware. It examines the planned integration flow along with specific reactor requirements that affect the spacecraft integration including American-Russian space system compatibility.

  10. Mission analysis for hybrid thermionic nuclear reactor LEO-to-GEO transfer applications

    SciTech Connect (OSTI)

    Widman, F.W. Jr.; North, D.M. (Rockwell International/Rocketdyne Division, 6633 Canoga Avenue, Canoga Park, California 91303 (United States)); Choong, P.T.; Teofilo, V.L. (Lockheed Missiles and Space Company, Inc., 1111 Lockheed Way, Synnyvale, California 94088 (United States))

    1993-01-10T23:59:59.000Z

    This paper details the results of mission analyses concerning a hybrid STAR-C based system, which is based on a safe solid fuel form for high-temperature reactor core operation and a rugged planar thermionic energy converter for long-life steady-state electric power production. Hybrid power/propulsion system concepts are shown to offer superior performance capabilities for Low-Earth-Orbit (LEO) to Geosynchronous-Earth-Orbit (GEO) orbital transfer applications over chemical propulsion systems. A key feature of the hybrid power/propulsion system is that the propulsion system uses the on-board payload power system. Mission results for hybrid concepts using Nuclear Thermal Propulsion (NTP), Nuclear Electric Propulsion (NEP), and combination of NTP and NEP are discussed.

  11. Investigation of the organic matter in inactive nuclear tank liquids. Environmental Restoration Program

    SciTech Connect (OSTI)

    Schenley, R.L.; Griest, W.H.

    1990-08-01T23:59:59.000Z

    Environmental Protection Agency (EPA) methodology for regulatory organics fails to account for the organic matter that is suggested by total organic carbon (TOC) analysis in the Oak Ridge National Laboratory (ORNL) inactive nuclear waste-tank liquids and sludges. Identification and measurement of the total organics are needed to select appropriate waste treatment technologies. An initial investigation was made of the nature of the organics in several waste-tank liquids. This report details the analysis of ORNL wastes.

  12. Interplanetary missions with the GDM propulsion system

    SciTech Connect (OSTI)

    Kammash, T.; Emrich, W. Jr. [Department of Nuclear Engineering and Radiological Sciences, University of Michigan, Ann Arbor, Michigan 48109 (United States); Marshall Space Flight Center, Huntsville, Alabama 35812 (United States)

    1998-01-15T23:59:59.000Z

    The Gasdynamic Mirror (GDM) fusion propulsion system utilizes a magnetic mirror machine in which a hot dense plasma is confined long enough to produce fusion energy while allowing a fraction of its charged particle population to escape from one end to generate thrust. The particles escaping through the opposite end have their energy converted to electric power which can be used to sustain the system in a steady state operation. With the aid of a power flow diagram the minimum demands on energy production can be established and the propulsive capability of the system can be determined by solving an appropriate set of governing equations. We apply these results to several missions within the solar system and compute the trip time by invoking a continuous burn, acceleration/deceleration type of trajectory with constant thrust and specific impulse. Ignoring gravitational effects of the planets or the sun, and neglecting the change in the Earth's position during the flight we compute the round trip time for missions from Earth to Mars, Jupiter, and Pluto using linear distances and certain payload fractions. We find that a round trip to Mars with the GDM rocket takes about 170 days while those to Jupiter and Pluto take 494 and 1566 days respectively.

  13. ab-ramjet space propulsion: Topics by E-print Network

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

    12 NASA Procedural Requirements NRPTA National Rocket Propulsion Testing Alliance OIG Office of Inspector General RPT Rocket Propulsion Test SLS Space Launch System...

  14. E-Print Network 3.0 - accent propulsion lander Sample Search...

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

    vehicle design and operations, propulsion, orbital mechanics, spacecraft... on hypersonic flight and electric rocket propulsion. Dr. Erwin teaches two lower-division...

  15. Startup control of the TOPAZ-II space nuclear reactor. Master`s thesis

    SciTech Connect (OSTI)

    Astrin, C.D.

    1996-09-01T23:59:59.000Z

    The Russian designed and manufactured TOPAZ-II Thermionic Nuclear Space Reactor has been supplied to the Ballistic Missile Defense Organization for study as part of the TOPAZ International Program. A Preliminary Nuclear Safety Assessment investigated the readiness to use the TOPAZ-II in support of a Nuclear Electric Propulsion Space Test Mission (NEPSTP). Among the anticipated system modifications required for launching the TOPAZ-II system within safety goals is for a U.S. designed Automatic Control System. The requirements and desired features of such a control system are developed based upon U.S. safety standards. System theory and design are presented in order to establish the basis for development of a hybrid control model from available simulations. The model is verified and then used in exploration of various control schemes and casualty analysis providing groundwork for future Automatic Control System design.

  16. Worker Protection Program for DOE (Including the National Nuclear Security Administration) Federal Employees

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

    2007-05-17T23:59:59.000Z

    The Order establishes the framework for an effective worker protection program that will reduce or prevent injuries, illnesses, and accidental losses by providing DOE and NNSA Federal workers with a safe and healthful workplace. Chg 1 dated 8-21-12. Cancels DOE M 440.1-1A. Admin Chg 1, dated 3-14-13.

  17. Development of a criticality safety program guide for DOE nonreactor nuclear facilities

    SciTech Connect (OSTI)

    Hopper, C.M. [Oak Ridge National Lab., TN (United States)

    1994-09-01T23:59:59.000Z

    The objective of this paper was a presentation and discussion of the US DOE`s efforts to develop a NCS program guide for the implementation of 10CFR830.380. Topics of discussion were: (1) introduction/general practices; (2) definition of terms; (3) administration; (4) NCSA guidelines; (5) calculations; (6) conduct of operations; (7) state support; and (8) emergency preparedness.

  18. R t f N l C t T ti Di i GReport of Nuclear Component Testing Discussion Group National Spherical Torus ProgramNational Spherical Torus Program

    E-Print Network [OSTI]

    Office of Science R t f N l C t T ti Di i GReport of Nuclear Component Testing Discussion Group nuclear technology, SG1 leader UCLA DOE contact: Eckstrand, Steve, OFES #12;Nuclear Component Testing (NCT) aims to complement ITER mission and fill many DEMO R&D gaps · Mission of the Nuclear Component Testing

  19. Order Module--DOE O 452.1D, NUCLEAR EXPLOSIVE AND WEAPON SURETY PROGRAM, DOE O 452.2D, NUCLEAR EXPLOSIVE SAFETY

    Broader source: Energy.gov [DOE]

    "To prevent accidents and inadvertent or unauthorized use of U.S. nuclear weapons and nuclear explosives. In conjunction with the Department of Defense (DoD), to protect the public health and...

  20. Nuclear Safety Research and Development Program Proposal Submittal Instructions for Fiscal Year 2015

    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 Technology Subcommittee of NEAC MujidDepartmentof Nuclear

  1. Nuclear Safety Research and Development (NSR&D) Program | Department of

    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:Year in3.pdfEnergyDepartment of Energy Advanced1, 2014NuclearCommission, Office

  2. Advanced Fusion Reactors for Space Propulsion and Power Systems

    SciTech Connect (OSTI)

    Chapman, John J.

    2011-06-15T23:59:59.000Z

    In recent years the methodology proposed for conversion of light elements into energy via fusion has made steady progress. Scientific studies and engineering efforts in advanced fusion systems designs have introduced some new concepts with unique aspects including consideration of Aneutronic fuels. The plant parameters for harnessing aneutronic fusion appear more exigent than those required for the conventional fusion fuel cycle. However aneutronic fusion propulsion plants for Space deployment will ultimately offer the possibility of enhanced performance from nuclear gain as compared to existing ionic engines as well as providing a clean solution to Planetary Protection considerations and requirements. Proton triggered 11Boron fuel (p- 11B) will produce abundant ion kinetic energy for In-Space vectored thrust. Thus energetic alpha particles' exhaust momentum can be used directly to produce high Isp thrust and also offer possibility of power conversion into electricity. p-11B is an advanced fusion plant fuel with well understood reaction kinematics but will require some new conceptual thinking as to the most effective implementation.

  3. Development of Liquid-Vapor Core Reactors with MHD Generator for Space Power and Propulsion Applications

    SciTech Connect (OSTI)

    Samim Anghaie

    2002-08-13T23:59:59.000Z

    Any reactor that utilizes fuel consisting of a fissile material in a gaseous state may be referred to as a gaseous core reactor (GCR). Studies on GCRs have primarily been limited to the conceptual phase, mostly due to budget cuts and program cancellations in the early 1970's. A few scientific experiments have been conducted on candidate concepts, primarily of static pressure fissile gas filling a cylindrical or spherical cavity surrounded by a moderating shell, such as beryllium, heavy water, or graphite. The main interest in this area of nuclear power generation is for space applications. The interest in space applications has developed due to the promise of significant enhancement in fuel utilization, safety, plant efficiency, special high-performance features, load-following capabilities, power conversion optimization, and other key aspects of nuclear power generation. The design of a successful GCR adapted for use in space is complicated. The fissile material studied in the pa st has been in a fluorine compound, either a tetrafluoride or a hexafluoride. Both of these molecules have an impact on the structural material used in the making of a GCR. Uranium hexafluoride as a fuel allows for a lower operating temperature, but at temperatures greater than 900K becomes essentially impossible to contain. This difficulty with the use of UF6 has caused engineers and scientists to use uranium tetrafluoride, which is a more stable molecule but has the disadvantage of requiring significantly higher operating temperatures. Gas core reactors have traditionally been studied in a steady state configuration. In this manner a fissile gas and working fluid are introduced into the core, called a cavity, that is surrounded by a reflector constructed of materials such as Be or BeO. These reactors have often been described as cavity reactors because the density of the fissile gas is low and criticality is achieved only by means of the reflector to reduce neutron leakage from the core. Still there are problems of containment since many of the proposed vessel materials such as W or Mo have high neutron cross sections making the design of a critical system difficult. There is also the possibility for a GCR to remain in a subcritical state, and by the use of a shockwave mechanism, increase the pressure and temperature inside the core to achieve criticality. This type of GCR is referred to as a shockwave-driven pulsed gas core reactor. These two basic designs were evaluated as advance concepts for space power and propulsion.

  4. Nuclear Explosive Safety

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

    2015-01-26T23:59:59.000Z

    This Department of Energy (DOE) Order establishes requirements to implement the nuclear explosive safety (NES) elements of DOE O 452.1E, Nuclear Explosive and Weapon Surety Program, or successor directive, for routine and planned nuclear explosive operations (NEOs).

  5. Nuclear Explosive Safety

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

    2014-07-10T23:59:59.000Z

    The Order establishes requirements to implement the nuclear explosive safety (NES) elements of DOE O 452.1E, Nuclear Explosive and Weapon Surety Program, for routine and planned nuclear explosive operations (NEOs).

  6. Nuclear Safety (Pennsylvania)

    Broader source: Energy.gov [DOE]

    The Nuclear Safety Division conducts a comprehensive nuclear power plant oversight review program of the nine reactors at the five nuclear power sites in Pennsylvania. It also monitors the...

  7. RISKIND: A computer program for calculating radiological consequences and health risks from transportation of spent nuclear fuel

    SciTech Connect (OSTI)

    Yuan, Y.C. [Square Y Consultants, Orchard Park, NY (US); Chen, S.Y.; Biwer, B.M.; LePoire, D.J. [Argonne National Lab., IL (US)

    1995-11-01T23:59:59.000Z

    This report presents the technical details of RISKIND, a computer code designed to estimate potential radiological consequences and health risks to individuals and the collective population from exposures associated with the transportation of spent nuclear fuel. RISKIND is a user-friendly, interactive program that can be run on an IBM or equivalent personal computer under the Windows{trademark} environment. Several models are included in RISKIND that have been tailored to calculate the exposure to individuals under various incident-free and accident conditions. The incident-free models assess exposures from both gamma and neutron radiation and can account for different cask designs. The accident models include accidental release, atmospheric transport, and the environmental pathways of radionuclides from spent fuels; these models also assess health risks to individuals and the collective population. The models are supported by databases that are specific to spent nuclear fuels and include a radionuclide inventory and dose conversion factors. In addition, the flexibility of the models allows them to be used for assessing any accidental release involving radioactive materials. The RISKIND code allows for user-specified accident scenarios as well as receptor locations under various exposure conditions, thereby facilitating the estimation of radiological consequences and health risks for individuals. Median (50% probability) and typical worst-case (less than 5% probability of being exceeded) doses and health consequences from potential accidental releases can be calculated by constructing a cumulative dose/probability distribution curve for a complete matrix of site joint-wind-frequency data. These consequence results, together with the estimated probability of the entire spectrum of potential accidents, form a comprehensive, probabilistic risk assessment of a spent nuclear fuel transportation accident.

  8. Worker Protection Program for DOE (Including the National Nuclear Security Administration) Federal Employees

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

    2007-05-17T23:59:59.000Z

    The Order establishes the framework for an effective worker protection program that will reduce or prevent injuries, illnesses, and accidental losses by providing DOE and NNSA Federal workers with a safe and healthful workplace. Chg 1 dated 8-21-12, cancels DOE M 440.1-1A. Admin Chg 1, dated 3-14-13, cancels DOE O 440.1B Chg 1.

  9. DOE Vehicle Technologies Program 2009 Merit Review Report - Propulsion...

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

    for n-type (In,R)Co 4 Sb 12 Compositions, Introduce Single & Multiple "Rattlers" (In, Rare Earth) in Co 0.6 Rh 0.4 SbO 3 , Characterize TE Properties & Validate with Third Party...

  10. 2010 DOE EERE Vehicle Technologies Program Merit Review - Propulsion

    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 from theDepartment( Sample of ShipmentSimulation, AnalysisofCombustion |Materials

  11. DOE Vehicle Technologies Program 2009 Merit Review Report - Propulsion

    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-UpHeat Pump Models | Department of EnergyJanuaryTransmissionMaterials | Department of

  12. Nuclear systems and testing programs for ITER. Progress report for FY 1998

    SciTech Connect (OSTI)

    NONE

    1998-12-31T23:59:59.000Z

    The effort during this performance period focused on a number of TBWG activities (including test module design and analysis) that were identified and agreed upon (in the presence of the ITER Director and Deputy Director) at TBWG-4. These include: (a) DEMO test module design and performance analysis under pulsed operation; (b) Test program operation plan; (c) Test port design and analysis; (d) Decay heat calculations and safety analysis; (e) Further discussion among the parties to define collaboratory on R and D for the test program as well as possible collaboration on the construction and operation of test articles; (f) Remote handling and ancillary equipment; (g) Criteria for qualifying a blanket module or submodule for actual insertion and testing in ITER; (h) Definition of test module instrumentation and verification of capability to perform in the ITER fusion environment (magnetic field, radiation, heating, etc.); and (i) Analysis to show that the results to be obtained from the test modules as designed can be extrapolated to DEMO and reactor conditions (e.g., higher wall loads and the need to demonstrate tritium self-sufficiency). The main achievements during this performance period include: (1) updating and finalizing the US DDDs for the ITER Blanket Program to form part of the ITER Final Design Report (FDR). Specific revisions were in response to the minimal lithium volume test blanket design requirements and safety impact and (2) evaluating the feasibility of the US test program, including instrumentation and the benefits of the ITER test program. Details of this assessment, including solid breeder and liquid breeder blanket test plans, are documented in UCLA-IFNT-13 (attached). In addition, dose mapping calculations were performed for the ITER Building, including equipment and layout of coolant pipes/heat exchangers. A report on ITER Building dose calculations was sent to UD ITER management and to the Garching Task Coordinator in April, 1998. The report entitled Three-Dimensional Calculations of ITER Building Dose Rate Profiles and Assessment of Accessibility Inside the Building During Operation and After Shutdown of ITER can be located through ITER Reference Number of ITER Task S 62 TD 12, ID No: D325 ITER/US/98/S62TD12-D325 UCLA-FNT-100 UCLA-ENG-98-190.

  13. Radioisotope-powered cardiac pacemaker program. Clinical studies of the nuclear pacemaker model NU-5. Final report

    SciTech Connect (OSTI)

    Not Available

    1980-06-01T23:59:59.000Z

    Beginning in February, 1970, the Nuclear Materials and Equipment Corporation (NUMEC) undertook a program to design, develop and manufacture a radioisotope powered cardiac pacemaker system. The scope of technical work was specified to be: establish system, component, and process cost reduction goals using the prototype Radioisotope Powered Cardiac Pacemaker (RCP) design and develop production techniques to achieve these cost reduction objectives; fabricate radioisotope powered fueled prototype cardiac pacemakers (RCP's) on a pilot production basis; conduct liaison with a Government-designated fueling facility for purposes of defining fueling requirements, fabrication and encapsulation procedures, safety design criteria and quality control and inspection requirements; develop and implement Quality Assurance and Reliability Programs; conduct performance, acceptance, lifetime and reliability tests of fueled RCP's in the laboratory; conduct liaison with the National Institutes of Health and with Government specified medical research institutions selected for the purpose of undertaking clinical evaluation of the RCP in humans; monitor and evaluate, on a continuing basis, all test data; and perform necessary safety analyses and tests. Pacemaker designs were developed and quality assurance and manufacturing procedures established. Prototype pacemakers were fabricated. A total of 126 radioisotope powered units were implanted and have been followed clinically for approximately seven years. Four (4) of these units have failed. Eighty-three (83) units remain implanted and satisfactorily operational. An overall failure rate of less than the target 0.15% per month has been achieved.

  14. Nye County Nuclear Waste Repository Project Office independent scientific investigations program annual report, May 1997--April 1998

    SciTech Connect (OSTI)

    NONE

    1998-07-01T23:59:59.000Z

    This annual summary report, prepared by the Nye County Nuclear Waste Repository Project Office (NWRPO), summarizes the activities that were performed during the period from May 1, 1997 to April 30, 1998. These activities were conducted in support of the Independent Scientific Investigation Program (ISIP) of Nye County at the Yucca Mountain Site (YMS). The Nye County NWRPO is responsible for protecting the health and safety of the Nye County residents. NWRPO`s on-site representative is responsible for designing and implementing the Independent Scientific Investigation Program (ISIP). Major objectives of the ISIP include: Investigating key issues related to conceptual design and performance of the repository that can have major impact on human health, safety, and the environment; identifying areas not being addressed adequately by the Department of Energy (DOE). Nye County has identified several key scientific issues of concern that may affect repository design and performance which were not being adequately addressed by DOE. Nye County has been conducting its own independent study to evaluate the significance of these issues. This report summarizes the results of monitoring from two boreholes and the Exploratory Studies Facility (ESF) tunnel that have been instrumented by Nye County since March and April of 1995. The preliminary data and interpretations presented in this report do not constitute and should not be considered as the official position of Nye County. The ISIP presently includes borehole and tunnel instrumentation, monitoring, data analysis, and numerical modeling activities to address the concerns of Nye County.

  15. Nuclear Medicine Program progress report for quarter ending June 30, 1991

    SciTech Connect (OSTI)

    Knapp, F.F. Jr.; Ambrose, K.R.; Callahan, A.P.; McPherson, D.W.; Mirzadeh, S.; Srivastava, P.C.; Hasan, A.; Lambert, C.R.; Lambert, S.J.; Rice, D.E.

    1991-09-01T23:59:59.000Z

    In this report the excitation functions for production of gallium-66 via {alpha}-induced nuclear reactions on enriched zinc-66 have been measured with E{sub {alpha}}{le}27.3 Mev and E{sub {alpha}}{le}43.7 MeV employing the stack thin-target technique. In addition, the induced activity of gallium-67 in the same sets of targets allowed an evaluation of the excitation functions of the corresponding nuclear reactions. These preliminary studies have demonstrated that sufficient levels of gallium-66 can be produced by {alpha}-induced reactions on enriched zinc targets. A series of radioiodinated analogues of 1-azabicyclo(2.2.2)oct-3-yl {alpha}-hydroxy-{alpha}, {alpha}-diphenylacetate (QNB) have been prepared. These new analogues include 1-azabicyclo-(2.2.2)oct-3-yl{alpha}-hydroxy-{alpha}-(4-iodophenyl)-{alpha}-methylacetate(2,I-WNA), 1-azabicyclo(2.2.2)oct-3-yl (3-iodo)-xanthene-9-carboxylate (3,I-QNX), and 1-azabicyclo(2.2.2)oct-3-yl {alpha}-hydroxy-{alpha}-(E-1-iodo-1-propen-3-yl)-{alpha}-phenylacetate (4,I-QNP), which have also been radiolabeled with iodine-125 with high specific activity. The biodistribution, brain uptake, and receptor specificity of these new analogues are currently being studied. Shipments of radioactive agents made to collaborators during this period included. One shipment of iodine-125-labeled 15-(p-iodophenyl)-3-R,S-methylpentadecanoic acid (BMIPP) and tungsten-188/rhenium-188 generator. 16 refs., 7 figs., 1 tab.

  16. Before joining NSF as a program director for the Experimental Nuclear Physics pr

    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 MayAtmospheric Optical Depth (AOD)ProductssondeadjustsondeadjustAboutScience ProgramBackground8.0.1Vulture SpatialBECOME Ajoining NSF as a

  17. UNIVERSITY OF CALIFORNIA, BERKELEY Responses to Questions on the Future of University Nuclear Science and Engineering Programs

    E-Print Network [OSTI]

    Kammen, Daniel M.

    of these would be nuclear engineers? As described below, my estimate for the number of new engineers needed is under 1,000. At present 20% of nuclear engineering graduates enter the commercial nuclear energy work of nuclear engineers that are #12;currently produced at the undergraduate and graduate levels (345 in 2003

  18. Nuclear Medicine Program progress report for quarter ending September 30, 1992

    SciTech Connect (OSTI)

    Knapp, F.F. Jr.; Ambrose, K.R.; Beets, A.L.; Callahan, A.P.; McPherson, D.W.; Mirzadeh, S.; Hasan, A.; Lambert, C.R.

    1992-12-01T23:59:59.000Z

    The radioiodination and in vivo evaluation of p-iodocaramiphen a muscarinic antagonist which binds with high affinity to the M{sub 1} receptor subtype in vitro are described. Biodistribution studies in female Fischer rats demonstrated that [{sup 125}I]-piodocaraminphen had significant cerebral localization, but the uptake did not demonstrate specific uptake in those cerebral regions rich in muscarinic receptors, and radioactivity washed out rapidly from the brain. In addition there was no significant blockage of activity when the rats were preinjected with quinuclidinyl benzilate. These results suggest that p-iodocaramiphen is not a good candidate for the in vivo study of M{sub 1} muscarinic receptor populations by SPECT. Because of the widespread interest and expected importance of the availability of large amounts of tungsten-188 required for the tungsten-188/rhenium-188 generator systems, we have investigated the large-scale production of tungsten-188 in the ORNL HFIR. We have also compared our production data with the theoretical production values and with experimental data available in the literature from other reactors. Tungsten-188 is produced in a fission nuclear reactor by double neutron capture of tungsten-186. The experimental yield of tungsten-188 is approximately 4 mCi/mg of tungsten-186 at the end of bombardment (EOB) in the HFIR operating at 85 MWt power for a one cycle irradiation ({approximately}21 days) at a thermal neutron flux of 2 {times} 10{sup 15} n.s{sup {minus}1}cm{sup {minus}2}.

  19. Nuclear Medicine Program progress report for quarter ending September 30, 1992

    SciTech Connect (OSTI)

    Knapp, F.F. Jr.; Ambrose, K.R.; Beets, A.L.; Callahan, A.P.; McPherson, D.W.; Mirzadeh, S.; Hasan, A.; Lambert, C.R.

    1992-12-01T23:59:59.000Z

    The radioiodination and in vivo evaluation of p-iodocaramiphen a muscarinic antagonist which binds with high affinity to the M[sub 1] receptor subtype in vitro are described. Biodistribution studies in female Fischer rats demonstrated that [[sup 125]I]-piodocaraminphen had significant cerebral localization, but the uptake did not demonstrate specific uptake in those cerebral regions rich in muscarinic receptors, and radioactivity washed out rapidly from the brain. In addition there was no significant blockage of activity when the rats were preinjected with quinuclidinyl benzilate. These results suggest that p-iodocaramiphen is not a good candidate for the in vivo study of M[sub 1] muscarinic receptor populations by SPECT. Because of the widespread interest and expected importance of the availability of large amounts of tungsten-188 required for the tungsten-188/rhenium-188 generator systems, we have investigated the large-scale production of tungsten-188 in the ORNL HFIR. We have also compared our production data with the theoretical production values and with experimental data available in the literature from other reactors. Tungsten-188 is produced in a fission nuclear reactor by double neutron capture of tungsten-186. The experimental yield of tungsten-188 is approximately 4 mCi/mg of tungsten-186 at the end of bombardment (EOB) in the HFIR operating at 85 MWt power for a one cycle irradiation ([approximately]21 days) at a thermal neutron flux of 2 [times] 10[sup 15] n.s[sup [minus]1]cm[sup [minus]2].

  20. Annual Report Nucelar Energy Research and Development Program Nuclear Energy Research Initiative

    SciTech Connect (OSTI)

    Hively, LM

    2003-02-13T23:59:59.000Z

    NERI Project No.2000-0109 began in August 2000 and has three tasks. The first project year addressed Task 1, namely development of nonlinear prognostication for critical equipment in nuclear power facilities. That work is described in the first year's annual report (ORNLTM-2001/195). The current (second) project year (FY02) addresses Task 2, while the third project year will address Tasks 2-3. This report describes the work for the second project year, spanning August 2001 through August 2002, including status of the tasks, issues and concerns, cost performance, and status summary of tasks. The objective of the second project year's work is a compelling demonstration of the nonlinear prognostication algorithm using much more data. The guidance from Dr. Madeline Feltus (DOE/NE-20) is that it would be preferable to show forewarning of failure for different kinds of nuclear-grade equipment, as opposed to many different failure modes from one piece of equipment. Long-term monitoring of operational utility equipment is possible in principle, but is not practically feasible for the following reason. Time and funding constraints for this project do not allow us to monitor the many machines (thousands) that will be necessary to obtain even a few failure sequences, due to low failure rates (<10{sup -3}/year) in the operational environment. Moreover, the ONLY way to guarantee a controlled failure sequence is to seed progressively larger faults in the equipment or to overload the equipment for accelerated tests. Both of these approaches are infeasible for operational utility machinery, but are straight-forward in a test environment. Our subcontractor has provided such test sequences. Thus, we have revised Tasks 2.1-2.4 to analyze archival test data from such tests. The second phase of our work involves validation of the nonlinear prognostication over the second and third years of the proposed work. Recognizing the inherent limitations outlined in the previous paragraph, Dr. Feltus urged Oak Ridge National Laboratory (ORNL) to contact other researchers for additional data from other test equipment. Consequently, we have revised the work plan for Tasks 2.1-2.2, with corresponding changes to the work plan as shown in the Status Summary of NERI Tasks. The revised tasks are as follows: Task 2.1--ORNL will obtain test data from a subcontractor and other researchers for various test equipment. This task includes development of a test plan or a description of the historical testing, as appropriate: test facility, equipment to be tested, choice of failure mode(s), testing protocol, data acquisition equipment, and resulting data from the test sequence. ORNL will analyze this data for quality, and subsequently via the nonlinear paradigm for prognostication. Task 2.2--ORNL will evaluate the prognostication capability of the nonlinear paradigm. The comparison metrics for reliability of the predictions will include the true positives, true negatives, and the forewarning times. Task 2.3--ORNL will improve the nonlinear paradigm as appropriate, in accord with the results of Tasks 2.1-2.2, to maximize the rate of true positive and true negative indications of failure. Maximal forewarning time is also highly desirable. Task 2.4--ORNL will develop advanced algorithms for the phase-space distribution function (PS-DF) pattern change recognition, based on the results of Task 2.3. This implementation will provide a capability for automated prognostication, as part of the maintenance decision-making. Appendix A provides a detailed description of the analysis methods, which include conventional statistics, traditional nonlinear measures, and ORNL's patented nonlinear PSDM. The body of this report focuses on results of this analysis.

  1. Application of Diagnostic/Prognostic Methods to Critical Equipment for the Spent Nuclear Fuel Cleanup Program

    SciTech Connect (OSTI)

    Casazza, Lawrence O.; Jarrell, Donald B.; Koehler, Theresa M.; Meador, Richard J.; Wallace, Dale E.

    2002-02-28T23:59:59.000Z

    The management of the Spent Nuclear Fuel (SNF) project at the Hanford K-Basin in the 100 N Area has successfully restructured the preventive maintenance, spare parts inventory requirements, and the operator rounds data requirements. In this investigation, they continue to examine the different facets of the operations and maintenance (O&M) of the K-Basin cleanup project in search of additional reliability and cost savings. This report focuses on the initial findings of a team of PNNL engineers engaged to identify potential opportunities for reducing the cost of O&M through the application of advanced diagnostics (fault determination) and prognostics (residual life/reliability determination). The objective is to introduce predictive technologies to eliminate or reduce high impact equipment failures. The PNNL team in conjunction with the SNF engineers found the following major opportunities for cost reduction and/or enhancing reliability: (1) Provide data routing and automated analysis from existing detection systems to a display center that will engage the operations and engineering team. This display will be operator intuitive with system alarms and integrated diagnostic capability. (2) Change operating methods to reduce major transients induced in critical equipment. This would reduce stress levels on critical equipment. (3) Install a limited sensor set on failure prone critical equipment to allow degradation or stressor levels to be monitored and alarmed. This would provide operators and engineers with advance guidance and warning of failure events. Specific methods for implementation of the above improvement opportunities are provided in the recommendations. They include an Integrated Water Treatment System (IWTS) decision support system, introduction of variable frequency drives on certain pump motors, and the addition of limited diagnostic instrumentation on specified critical equipment.

  2. Sandia National Laboratories performance assessment methodology for long-term environmental programs : the history of nuclear waste management.

    SciTech Connect (OSTI)

    Marietta, Melvin Gary; Anderson, D. Richard; Bonano, Evaristo J.; Meacham, Paul Gregory (Raytheon Ktech, Albuquerque, NM)

    2011-11-01T23:59:59.000Z

    Sandia National Laboratories (SNL) is the world leader in the development of the detailed science underpinning the application of a probabilistic risk assessment methodology, referred to in this report as performance assessment (PA), for (1) understanding and forecasting the long-term behavior of a radioactive waste disposal system, (2) estimating the ability of the disposal system and its various components to isolate the waste, (3) developing regulations, (4) implementing programs to estimate the safety that the system can afford to individuals and to the environment, and (5) demonstrating compliance with the attendant regulatory requirements. This report documents the evolution of the SNL PA methodology from inception in the mid-1970s, summarizing major SNL PA applications including: the Subseabed Disposal Project PAs for high-level radioactive waste; the Waste Isolation Pilot Plant PAs for disposal of defense transuranic waste; the Yucca Mountain Project total system PAs for deep geologic disposal of spent nuclear fuel and high-level radioactive waste; PAs for the Greater Confinement Borehole Disposal boreholes at the Nevada National Security Site; and PA evaluations for disposal of high-level wastes and Department of Energy spent nuclear fuels stored at Idaho National Laboratory. In addition, the report summarizes smaller PA programs for long-term cover systems implemented for the Monticello, Utah, mill-tailings repository; a PA for the SNL Mixed Waste Landfill in support of environmental restoration; PA support for radioactive waste management efforts in Egypt, Iraq, and Taiwan; and, most recently, PAs for analysis of alternative high-level radioactive waste disposal strategies including repositories deep borehole disposal and geologic repositories in shale and granite. Finally, this report summarizes the extension of the PA methodology for radioactive waste disposal toward development of an enhanced PA system for carbon sequestration and storage systems. These efforts have produced a generic PA methodology for the evaluation of waste management systems that has gained wide acceptance within the international community. This report documents how this methodology has been used as an effective management tool to evaluate different disposal designs and sites; inform development of regulatory requirements; identify, prioritize, and guide research aimed at reducing uncertainties for objective estimations of risk; and support safety assessments.

  3. Nuclear medicine program progress report for quarter ending December 31, 1992

    SciTech Connect (OSTI)

    Knapp, F.F. Jr.; Ambrose, K.R.; Beets, A.L.; Callahan, A.P.; McPherson, D.W.; Mirzadeh, S.; Hasan, A.; Lambert, C.R.

    1993-03-01T23:59:59.000Z

    We describe the synthesis of the cis- and trans-iodovinyl isomers of the new ORNL cholinergic-muscarinicreceptorligand, 1 -azabicyclo[2.2-2]oct-3-yl[alpha]-hydroxy-[alpha]-(1-iodo-l-propen-3-yl)-[alpha]-phenylacetate ( IQNP''). This agent is prepared in high radiochemical yield, and the racemic mixture shows high specificity and selectivity for the cerebral and myocardial receptors. Since two chiral centers are present in this molecule, it is important to evaluate the importance of the absolute configuration of the two centers on receptor specificity. The tributyltin substrates were carefully separated by column chromatography, converted to the iodine-125 analogues by iododestannylation, and evaluated in rats in vivo. While the E'' (trans) isomer cleared rapidly from the receptor-rich areas of rat brain, the Z'' (cis) isomer showed high uptake in these areas but also high concentration in the cerebellum. In contrast, the E,Z-isomeric mixture showed good uptake and retention in the receptor rich areas. Also described in this report is a description of neutron flux measurements in the hydraulic tube position at the ORNL High Flux Isotope Reactor (HFIR). Also during this period, samples of [l-125]- and [l-131]-labeled racemic IQNP'' were supplied through a collaborative program with the Brookhaven National Laboratory for high resolution autoradiographic studies in rat tissues.

  4. Nuclear medicine program progress report for quarter ending December 31, 1992

    SciTech Connect (OSTI)

    Knapp, F.F. Jr.; Ambrose, K.R.; Beets, A.L.; Callahan, A.P.; McPherson, D.W.; Mirzadeh, S.; Hasan, A.; Lambert, C.R.

    1993-03-01T23:59:59.000Z

    We describe the synthesis of the cis- and trans-iodovinyl isomers of the new ORNL cholinergic-muscarinicreceptorligand, 1 -azabicyclo[2.2-2]oct-3-yl{alpha}-hydroxy-{alpha}-(1-iodo-l-propen-3-yl)-{alpha}-phenylacetate (``IQNP``). This agent is prepared in high radiochemical yield, and the racemic mixture shows high specificity and selectivity for the cerebral and myocardial receptors. Since two chiral centers are present in this molecule, it is important to evaluate the importance of the absolute configuration of the two centers on receptor specificity. The tributyltin substrates were carefully separated by column chromatography, converted to the iodine-125 analogues by iododestannylation, and evaluated in rats in vivo. While the ``E`` (trans) isomer cleared rapidly from the receptor-rich areas of rat brain, the ``Z`` (cis) isomer showed high uptake in these areas but also high concentration in the cerebellum. In contrast, the E,Z-isomeric mixture showed good uptake and retention in the receptor rich areas. Also described in this report is a description of neutron flux measurements in the hydraulic tube position at the ORNL High Flux Isotope Reactor (HFIR). Also during this period, samples of [l-125]- and [l-131]-labeled racemic ``IQNP`` were supplied through a collaborative program with the Brookhaven National Laboratory for high resolution autoradiographic studies in rat tissues.

  5. Development of a high power density motor for aircraft propulsion

    E-Print Network [OSTI]

    Dibua, Imoukhuede Tim Odion

    2007-04-25T23:59:59.000Z

    are currently powered by heavy gas turbine engines that require fueling. The development of electric motors to replace gas turbines would be a big step towards accomplishing more efficient aircraft propulsion. The primary objective of this research extends...

  6. Porous material and process development for electrospray propulsion applications

    E-Print Network [OSTI]

    Arestie, Steven Mark

    2014-01-01T23:59:59.000Z

    Ion electrospray propulsion devices rely on the transportation of ionic liquid propellant to emission regions where ions are extracted at high velocities. One such method involves the use of porous substrates to passively ...

  7. Molecular Dynamics Modeling of Ionic Liquids in Electrospray Propulsion

    E-Print Network [OSTI]

    . Lozano June 2010 SSL # 6-10 #12;#12;Molecular Dynamics Modeling of Ionic Liquids in Electrospray Propulsion Nanako Takahashi, Paulo C. Lozano June 2010 SSL # 6-10 This work is based on the unaltered text

  8. Electromagnetic Extraction and Annihilation of Antiprotons for Spacecraft Propulsion

    E-Print Network [OSTI]

    . Zayas, Raymond J. Sedwick May, 2008 SSL # 3-08 #12;#12;Electromagnetic Extraction and Annihilation of Antiprotons for Spacecraft Propulsion Daniel A. Zayas, Raymond J. Sedwick May, 2008 SSL # 3-08 This work

  9. A doubly-fed machine for propulsion applications

    E-Print Network [OSTI]

    Tomovich, Michael S. (Michael Stephen)

    2014-01-01T23:59:59.000Z

    A doubly fed machine for propulsion applications is proposed, which, given the presence of AC and DC power sources, can be utilized in order to improve efficiency, weight, volume, and sizing of the rotor power electronics. ...

  10. Novel turbomachinery concepts for highly integrated airframe/propulsion systems

    E-Print Network [OSTI]

    Shah, Parthiv N

    2007-01-01T23:59:59.000Z

    Two novel turbomachinery concepts are presented as enablers to advanced flight missions requiring integrated airframe/propulsion systems. The first concept is motivated by thermal management challenges in low-to-high Mach ...

  11. Molecular dynamics modeling of ionic liquids in electrospray propulsion

    E-Print Network [OSTI]

    Takahashi, Nanako

    2010-01-01T23:59:59.000Z

    Micro-propulsion has been studied for many years due to its applications in small-to-medium sized spacecraft for precise satellite attitude control. Electrospray thrusters are promising thrusters built upon the state of ...

  12. Emission spectroscopy for the study of electric propulsion plasmas

    E-Print Network [OSTI]

    Matlock, Taylor Scott

    2009-01-01T23:59:59.000Z

    Typical electric propulsion devices rely on the acceleration of highly ionized plasmas to produce thrust at specific impulses unattainable with state-of-the-art chemical systems. This thesis examines the use of a miniaturized ...

  13. Propulsion devices for locomotion at low-Reynolds number

    E-Print Network [OSTI]

    Chan, Brian, 1980-

    2004-01-01T23:59:59.000Z

    We have designed, built, and tested three novel devices that use low-Reynolds number flows for self propulsion. The three-link swimmer is designed to swim through in a free viscous fluid using cyclic flipping motion of two ...

  14. Design of repeating projectile toy based on bistable spring propulsion

    E-Print Network [OSTI]

    Blanco, Matthew C. (Matthew Corwin)

    2007-01-01T23:59:59.000Z

    Recently, bistable springs have been proven as a viable propulsion method for the standard 1.75" foam balls used in Nerf projectile toys. This technology was developed at M.I.T. by William Fienup and Barry Kudrowitz, who ...

  15. Diffusion driven object propulsion in density stratified fluids

    E-Print Network [OSTI]

    Lenahan, Conor (Conor P.)

    2009-01-01T23:59:59.000Z

    An experimental study was conducted in order to verify the appropriateness of a two dimensional model of the flow creating diffusion driven object propulsion in density stratified fluids. Initial flow field experiments ...

  16. Application of ion electrospray propulsion to lunar and interplanetary missions

    E-Print Network [OSTI]

    Whitlock, Caleb W. (Caleb Wade)

    2014-01-01T23:59:59.000Z

    High specific impulse electric propulsion systems enable ambitious lunar and interplanetary missions that return a wealth of scientific data. Many of these technologies are difficult to scale down, meaning the spacecraft ...

  17. Rocketdyne Propulsion and Power DOE Operations annual site environmental report 1997

    SciTech Connect (OSTI)

    Robinson, K.S. [ed.

    1998-11-23T23:59:59.000Z

    This annual report discusses environmental monitoring at two manufacturing and test sites operated in the Los Angeles area by Rocketdyne Propulsion and Power of Boeing North American, Inc. These are identified as Area 4 of the SSFL and the De Soto site. These sites have been used for research and development (R and D), engineering, and testing in a broad range of technical fields primarily in energy research and nuclear reactor technology. The De Soto site had research and development laboratories involved with nuclear research. This work was terminated in 1995 and only D and D activities will have potential for impact on the environment. Since 1956, Area 4 has been used for work with nuclear materials, including fabricating nuclear reactor fuels, testing nuclear reactors, and dissembling used fuel elements. This work ended in 1988 and subsequent efforts have been directed toward decommissioning and decontamination of the former nuclear facilities. The primary purpose of this report is to present information on environmental and effluent monitoring of DOE-sponsored activities to the regulatory agencies responsible for oversight. Information presented here concentrates on Area 4 at SSFL, which is the only area at SSFL where DOE operations were performed.

  18. Propulsion engineering study for small-scale Mars missions

    SciTech Connect (OSTI)

    Whitehead, J.

    1995-09-12T23:59:59.000Z

    Rocket propulsion options for small-scale Mars missions are presented and compared, particularly for the terminal landing maneuver and for sample return. Mars landing has a low propulsive {Delta}v requirement on a {approximately}1-minute time scale, but at a high acceleration. High thrust/weight liquid rocket technologies, or advanced pulse-capable solids, developed during the past decade for missile defense, are therefore more appropriate for small Mars landers than are conventional space propulsion technologies. The advanced liquid systems are characterize by compact lightweight thrusters having high chamber pressures and short lifetimes. Blowdown or regulated pressure-fed operation can satisfy the Mars landing requirement, but hardware mass can be reduced by using pumps. Aggressive terminal landing propulsion designs can enable post-landing hop maneuvers for some surface mobility. The Mars sample return mission requires a small high performance launcher having either solid motors or miniature pump-fed engines. Terminal propulsion for 100 kg Mars landers is within the realm of flight-proven thruster designs, but custom tankage is desirable. Landers on a 10 kg scale also are feasible, using technology that has been demonstrated but not previously flown in space. The number of sources and the selection of components are extremely limited on this smallest scale, so some customized hardware is required. A key characteristic of kilogram-scale propulsion is that gas jets are much lighter than liquid thrusters for reaction control. The mass and volume of tanks for inert gas can be eliminated by systems which generate gas as needed from a liquid or a solid, but these have virtually no space flight history. Mars return propulsion is a major engineering challenge; earth launch is the only previously-solved propulsion problem requiring similar or greater performance.

  19. Western Nuclear Science Alliance

    SciTech Connect (OSTI)

    Steve Reese; George Miller; Stephen Frantz; Denis Beller; Denis Beller; Ed Morse; Melinda Krahenbuhl; Bob Flocchini; Jim Elliston

    2010-12-07T23:59:59.000Z

    The primary objective of the INIE program is to strengthen nuclear science and engineering programs at the member institutions and to address the long term goal of the University Reactor Infrastructure and Education Assistance Program.

  20. Non Nuclear NTR Environmental Simulator

    SciTech Connect (OSTI)

    Emrich, William J. Jr. [NASA Marshall Space Flight Center, M.S. XD21, Huntsville, Alabama 35812 (United States)

    2006-01-20T23:59:59.000Z

    Nuclear Thermal Rockets or NTR's have been suggested as a propulsion system option for vehicles traveling to the moon or Mars. These engines are capable of providing high thrust at specific impulses at least twice that of today's best chemical engines. The performance constraints on these engines are mainly the result of temperature limitations on the fuel coupled with a limited ability to withstand chemical attack by the hot hydrogen propellant. To operate at maximum efficiency, fuel forms are desired which can withstand the extremely hot, hostile environment characteristic of NTR operation for at least several hours. The simulation of such an environment would require an experimental device which could simultaneously approximate the power, flow, and temperature conditions which a nuclear fuel element (or partial element) would encounter during NTR operation. Such a simulation would allow detailed studies of the fuel behavior and hydrogen flow characteristics under reactor like conditions to be performed. The goal of these simulations would be directed toward expanding the performance envelope of NTR engines over that which was demonstrated during the Rover and NERVA nuclear rocket programs of the 1970's. Current planning calls for such a simulator to be constructed at the Marshall Space Flight Center over the coming year, and it is anticipated that it will be used in the future to evaluate a wide variety of fuel element designs and the materials of which they are constructed. This present work addresses the initial experimental objectives of the NTR simulator with regard to reproducing the fuel degradation patterns previously observed during the NERVA testing.

  1. Death Valley Lower Carbonate Aquifer Monitoring Program Wells Down gradient of the Proposed Yucca Mountain Nuclear Waste Repository

    SciTech Connect (OSTI)

    Inyo County

    2006-07-26T23:59:59.000Z

    Inyo County has participated in oversight activities associated with the Yucca Mountain Nuclear Waste Repository since 1987. The overall goal of these studies are the evaluation of far-field issues related to potential transport, by ground water, or radionuclides into Inyo County, including Death Valley, and the evaluation of a connection between the Lower Carbonate Aquifer (LCA) and the biosphere. Our oversight and completed Cooperative Agreement research, and a number of other investigators research indicate that there is groundwater flow between the alluvial and carbonate aquifers both at Yucca Mountain and in Inyo County. In addition to the potential of radionuclide transport through the LCA, Czarnecki (1997), with the US Geological Survey, research indicate potential radionuclide transport through the shallower Tertiary-age aquifer materials with ultimate discharge into the Franklin Lake Playa in Inyo County. The specific purpose of this Cooperative Agreement drilling program was to acquire geological, subsurface geology, and hydrologic data to: (1) establish the existence of inter-basin flow between the Amargosa Basin and Death Valley Basin; (2) characterize groundwater flow paths in the LCA through Southern Funeral Mountain Range, and (3) Evaluation the hydraulic connection between the Yucca Mountain repository and the major springs in Death Valley through the LCA.

  2. Selection of Russian Plutonium Beryllium Sources for Inclusion in the Nuclear Mateirals Information Program Archive

    SciTech Connect (OSTI)

    Narlesky, Joshua E [Los Alamos National Laboratory; Padilla, Dennis D [Los Alamos National Laboratory; Watts, Joe [Los Alamos National Laboratory

    2009-01-01T23:59:59.000Z

    Throughout the 1960s and 1970s, the former Soviet Union produced and exported Plutonium-Beryllium (PuBe) neutron sources to various Eastern European countries. The Russian sources consist of an intermetallic compound of plutonium and beryllium encapsulated in an inner welded, sealed capsule and consisting of a body and one or more covers. The amount of plutonium in the sources ranges from 0.002 g up to 15 g. A portion of the sources was originally exported to East Germany. A portion of these sources were acquired by Los Alamos National Laboratory (LANL) in the late 1990s for destruction in the Offsite Source Recovery Program. When the OSRP was canceled, the remaining 88 PuBe neutron sources were packaged and stored in a 55-gal drum at T A-55. This storage configuration is no longer acceptable for PuBe sources, and the sources must either be repackaged or disposed of. Repackaging would place the sources into Hagan container, and depending on the dose rates, some sources may be packaged individually increasing the footprint and cost of storage. In addition, each source will be subject to leak-checking every six months. Leaks have already been detected in some of the sources, and due to the age of these sources, it is likely that additional leaks may be detected over time, which will increase the overall complexity of handling and storage. Therefore, it was decided that the sources would be disposed of at the Waste Isolation Pilot Plant (WIPP) due to the cost and labor associated with continued storage at TA-55. However, the plutonium in the sources is of Russian origin and needs to be preserved for research purposes. Therefore, it is important that a representative sample of the sources retained and archived for future studies. This report describes the criteria used to obtain a representative sample of the sources. Nine Russian PuBe neutron sources have been selected out of a collection of 77 sources for inclusion in the NMIP archive. Selection criteria were developed so that the largest sources that are representative of the collection are included. One representative source was chosen for every 20 sources in the collection, and effort was made to preserve sources unique to the collection. In total, four representative sources and five unique sources were selected for the archive. The archive samples contain 40 grams of plutonium with an isotopic composition similar to that of weapon grade material and three grams of plutonium with an isotopic composition similar to that of reactor grade plutonium.

  3. Program Mission Campaigns are multi-year, multi-functional efforts involving, to varying degrees, every site in the nuclear

    E-Print Network [OSTI]

    and reliability of aged and remanufactured weapons in the absence of nuclear testing. This technology base must with the cessation of underground nuclear testing. · Inertial Confinement Fusion Ignition and High Yield (ICF degrees, every site in the nuclear weapons complex. They provide specialized scientific knowledge

  4. Preparing Non-nuclear Engineers for the Nuclear Field

    E-Print Network [OSTI]

    Ervin, Elizabeth K.

    Preparing Non-nuclear Engineers for the Nuclear Field Elizabeth K. Ervin The University. An understanding of power generation is important for all modern-day engineers, and nuclear energy serves as a good-four universities have nuclear- related programs, including Nuclear or Radiological Engineering, Nuclear Science

  5. Nuclear Energy University Programs

    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 Careerlumens_placard-green.epsEnergy Second Quarter4, 2014 Dr.7446AugustJune

  6. Civilian Nuclear Programs

    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 May Jun Jul(Summary)morphinanInformation InInformationCenterResearchCASLNanoporous Materials | Center for GasChemical

  7. Aeronautics Test Program (ATP) Corporate Management of Aeronautical Facilities

    E-Print Network [OSTI]

    Aeronautics Test Program (ATP) Corporate Management of Aeronautical Facilities 44th AIAA Aerospace Propulsion Systems Lab. 3 & 4 · Glenn 10x10 Supersonic Tunnel ATP provides 60%- 75% of fixed costs #12

  8. Spent Nuclear Fuel Fact Sheets

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

    management needs. By coordinating common needs for research, technology development, and testing programs, the National Spent Nuclear Fuel Program is achieving cost efficiencies...

  9. Self-propulsion of V-shape micro-robot

    E-Print Network [OSTI]

    Vladimir A. Vladimirov

    2012-09-13T23:59:59.000Z

    In this paper we study the self-propulsion of a symmetric V-shape micro-robot (or V-robot) which consists of three spheres connected by two arms with an angle between them; the arms' lengths and the angle are changing periodically. Using an asymptotic procedure containing two-timing method and a distinguished limit, we obtain analytic expressions for the self-propulsion velocity and Lighthill's efficiency. The calculations show that a version of V-robot, aligned perpendicularly to the direction of self-swimming, is both the fastest one and the most efficient one. We have also shown that such $V$-robot is faster and more efficient than a linear three-sphere micro-robot. At the same time the maximal self-propulsion velocity of V-robots is significantly smaller than that of comparable microorganisms.

  10. Propulsion Mechanisms for Leidenfrost Solids on Ratchet Surfaces

    E-Print Network [OSTI]

    Baier, Tobias; Herbert, Stefan; Hardt, Steffen; Quere, David

    2012-01-01T23:59:59.000Z

    We propose a model for the propulsion of Leidenfrost solids on ratchets based on viscous drag due to the flow of evaporating vapor. The model assumes pressure-driven flow described by the Navier-Stokes equations and is mainly studied in lubrication approximation. A scaling expression is derived for the dependence of the propulsive force on geometric parameters of the ratchet surface and properties of the sublimating solid. We show that the model results as well as the scaling law compare favorably with experiments and are able to reproduce the experimentally observed scaling with the size of the solid.

  11. Naval ship propulsion and electric power systems selection for optimal fuel consumption

    E-Print Network [OSTI]

    Sarris, Emmanouil

    2011-01-01T23:59:59.000Z

    Although propulsion and electric power systems selection is an important part of naval ship design, respective decisions often have to be made without detailed ship knowledge (resistance, propulsors, etc.). Propulsion and ...

  12. High performance path following for marine vehicles using azimuthing podded propulsion

    E-Print Network [OSTI]

    Greytak, Matthew B. (Matthew Bardeen)

    2006-01-01T23:59:59.000Z

    Podded propulsion systems offer greater maneuvering possibilities for marine vehicles than conventional shaft and rudder systems. As the propulsion unit rotates about its vertical axis to a specified azimuth angle, the ...

  13. E-Print Network 3.0 - automotive-propulsion fuel cells Sample...

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

    automotive-propulsion fuel cells Search Powered by Explorit Topic List Advanced Search Sample search results for: automotive-propulsion fuel cells Page: << < 1 2 3 4 5 > >> 1 ORNL...

  14. The Development, Content, Design, and Conduct of the 2011 Piloted US DOE Nuclear Criticality Safety Program Criticality Safety Engineering Training and Education Project

    SciTech Connect (OSTI)

    Hopper, Calvin Mitchell [ORNL] [ORNL

    2011-01-01T23:59:59.000Z

    In May 1973 the University of New Mexico conducted the first nationwide criticality safety training and education week-long short course for nuclear criticality safety engineers. Subsequent to that course, the Los Alamos Critical Experiments Facility (LACEF) developed very successful 'hands-on' subcritical and critical training programs for operators, supervisors, and engineering staff. Since the inception of the US Department of Energy (DOE) Nuclear Criticality Technology and Safety Project (NCT&SP) in 1983, the DOE has stimulated contractor facilities and laboratories to collaborate in the furthering of nuclear criticality as a discipline. That effort included the education and training of nuclear criticality safety engineers (NCSEs). In 1985 a textbook was written that established a path toward formalizing education and training for NCSEs. Though the NCT&SP went through a brief hiatus from 1990 to 1992, other DOE-supported programs were evolving to the benefit of NCSE training and education. In 1993 the DOE established a Nuclear Criticality Safety Program (NCSP) and undertook a comprehensive development effort to expand the extant LACEF 'hands-on' course specifically for the education and training of NCSEs. That successful education and training was interrupted in 2006 for the closing of the LACEF and the accompanying movement of materials and critical experiment machines to the Nevada Test Site. Prior to that closing, the Lawrence Livermore National Laboratory (LLNL) was commissioned by the US DOE NCSP to establish an independent hands-on NCSE subcritical education and training course. The course provided an interim transition for the establishment of a reinvigorated and expanded two-week NCSE education and training program in 2011. The 2011 piloted two-week course was coordinated by the Oak Ridge National Laboratory (ORNL) and jointly conducted by the Los Alamos National Laboratory (LANL) classroom education and facility training, the Sandia National Laboratory (SNL) hands-on criticality experiments training, and the US DOE National Criticality Experiment Research Center (NCERC) hands-on criticality experiments training that is jointly supported by LLNL and LANL and located at the Nevada National Security Site (NNSS) This paper provides the description of the bases, content, and conduct of the piloted, and future US DOE NCSP Criticality Safety Engineer Training and Education Project.

  15. E-Print Network 3.0 - ab-thermonuclear space propulsion Sample...

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

    thermonuclear space propulsion Search Powered by Explorit Topic List Advanced Search Sample search results for: ab-thermonuclear...

  16. Nuclear weapons modernizations

    SciTech Connect (OSTI)

    Kristensen, Hans M. [Federation of American Scientists, Washington, DC (United States)

    2014-05-09T23:59:59.000Z

    This article reviews the nuclear weapons modernization programs underway in the world's nine nuclear weapons states. It concludes that despite significant reductions in overall weapons inventories since the end of the Cold War, the pace of reductions is slowing - four of the nuclear weapons states are even increasing their arsenals, and all the nuclear weapons states are busy modernizing their remaining arsenals in what appears to be a dynamic and counterproductive nuclear competition. The author questions whether perpetual modernization combined with no specific plan for the elimination of nuclear weapons is consistent with the nuclear Non-Proliferation Treaty and concludes that new limits on nuclear modernizations are needed.

  17. 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.

  18. International Electric Propulsion Conference, The George Washington University, USA October 6 10, 2013

    E-Print Network [OSTI]

    Walker, Mitchell

    1 The 33rd International Electric Propulsion Conference, The George Washington University, USA Electric Propulsion Conference, The George Washington University · Washington, D.C. · USA October 6 ­ 10.t.yim@nasa.gov. #12;2 The 33rd International Electric Propulsion Conference, The George Washington University, USA

  19. Nuclear facility decommissioning and site remedial actions: A selected bibliography, Volume 13: Part 2, Indexes. Environmental Restoration Program

    SciTech Connect (OSTI)

    Goins, L.F.; Webb, J.R.; Cravens, C.D.; Mallory, P.K.

    1992-09-01T23:59:59.000Z

    This is part 2 of a bibliography on nuclear facility decommissioning and site remedial action. This report contains indexes on the following: authors, corporate affiliation, title words, publication description, geographic location, subject category, and key word.

  20. Emissions and Performance Tradeoffs for Advanced Marine Diesel Propulsion

    E-Print Network [OSTI]

    Stefanopoulou, Anna

    the turbocharger and the diesel engine in steady-state 5]. Secondly, it modi es the power transfer to the turbineEmissions and Performance Tradeoffs for Advanced Marine Diesel Propulsion Anna Stefanopoulouy is designed that reduces smoke generation on an experimental marine Diesel engine equipped with a variable

  1. The Planning, Licensing, Modifications, and Use of a Russian Vessel for Shipping Spent Nuclear Fuel by Sea in Support of the DOE RRRFR Program

    SciTech Connect (OSTI)

    Michael Tyacke; Dr. Igor Bolshinsky; Wlodzimierz Tomczak; Sergey Naletov; Oleg Pichugin

    2001-10-01T23:59:59.000Z

    The Russian Research Reactor Fuel Return (RRRFR) Program, under the U.S. Department of Energys Global Threat Reduction Initiative, began returning Russian-supplied high-enriched uranium (HEU) spent nuclear fuel (SNF), stored at Russian-designed research reactors throughout the world, to Russia in January 2006. During the first years of making HEU SNF shipments, it became clear that the modes of transportation needed to be expanded from highway and railroad to include sea and air to meet the extremely aggressive commitment of completing the first series of shipments by the end of 2010. The first shipment using sea transport was made in October 2008 and used a non-Russian flagged vessel. The Russian government reluctantly allowed a one-time use of the foreign-owned vessel into their highly secured seaport, with the understanding that any future shipments would be made using a vessel owned and operated by a Russian company. ASPOL-Baltic of St. Petersburg, Russia, owns and operates a small fleet of vessels and has a history of shipping nuclear materials. ASPOL-Baltics vessels were licensed for shipping nuclear materials; however, they were not licensed to transport SNF materials. After a thorough review of ASPOL Baltics capabilities and detailed negotiations, it was agreed that a contract would be let with ASPOL-Baltic to license and refit their MCL Trader vessel for hauling SNF in support of the RRRFR Program. This effort was funded through a contract between the RRRFR Program, Idaho National Laboratory, and Radioactive Waste Management Plant of Swierk, Poland. This paper discusses planning, Russian and international maritime regulations and requirements, Russian authorities reviews and approvals, licensing, design, and modifications made to the vessel in preparation for SNF shipments. A brief summary of actual shipments using this vessel, experiences, and lessons learned also are described.

  2. Hybrid Vehicle Program. Final report

    SciTech Connect (OSTI)

    None

    1984-06-01T23:59:59.000Z

    This report summarizes the activities on the Hybrid Vehicle Program. The program objectives and the vehicle specifications are reviewed. The Hybrid Vehicle has been designed so that maximum use can be made of existing production components with a minimum compromise to program goals. The program status as of the February 9-10 Hardware Test Review is presented, and discussions of the vehicle subsystem, the hybrid propulsion subsystem, the battery subsystem, and the test mule programs are included. Other program aspects included are quality assurance and support equipment. 16 references, 132 figures, 47 tables.

  3. Structural Integrity Program for the 300,000-Gallon Radioactive Liquid Waste Storage Tanks at the Idaho Nuclear Technology and Engineering Center

    SciTech Connect (OSTI)

    Bryant, J.W.; Nenni, J.A.; Yoder, T.S.

    2003-04-22T23:59:59.000Z

    This report provides a record of the Structural Integrity Program for the 300,000-gal liquid waste storage tanks and associated equipment at the Idaho Nuclear Technology and Engineering Center, as required by U.S. Department of Energy M 435.1-1, ''Radioactive Waste Management Manual.'' This equipment is known collectively as the Tank Farm Facility. The conclusion of this report is that the Tank Farm Facility tanks, vaults, and transfer systems that remain in service for storage are structurally adequate, and are expected to remain structurally adequate over the remainder of their planned service life through 2012. Recommendations are provided for continued monitoring of the Tank Farm Facility.

  4. Structural Integrity Program for the 300,000-Gallon Radioactive Liquid Waste Tanks at the Idaho Nuclear Technology and Engineering Center

    SciTech Connect (OSTI)

    Bryant, Jeffrey Whealdon; Nenni, Joseph A; Timothy S. Yoder

    2003-04-01T23:59:59.000Z

    This report provides a record of the Structural Integrity Program for the 300,000-gal liquid waste storage tanks and associated equipment at the Idaho Nuclear Technology and Engineering Center, as required by U.S. Department of Energy M 435.1-1, Radioactive Waste Management Manual. This equipment is known collectively as the Tank Farm Facility. The conclusion of this report is that the Tank Farm Facility tanks, vaults, and transfer systems that remain in service for storage are structurally adequate, and are expected to remain structurally adequate over the remainder of their planned service life through 2012. Recommendations are provided for continued monitoring of the Tank Farm Facility.

  5. Heat pipe radiation cooling (HPRC) for high-speed aircraft propulsion. Phase 2 (feasibility) final report

    SciTech Connect (OSTI)

    Martin, R.A.; Merrigan, M.A.; Elder, M.G.; Sena, J.T.; Keddy, E.S. [Los Alamos National Lab., NM (United States); Silverstein, C.C. [CCS Associates, Bethel Park, PA (United States)

    1994-03-25T23:59:59.000Z

    The National Aeronautics and Space Administration (NASA), Los Alamos National Laboratory (Los Alamos), and CCS Associates are conducting the Heat Pipe Radiation Cooling (HPRC) for High-Speed Aircraft Propulsion program to determine the advantages and demonstrate the feasibility of using high-temperature heat pipes to cool hypersonic engine components. This innovative approach involves using heat pipes to transport heat away from the combustor, nozzle, or inlet regions, and to reject it to the environment by thermal radiation from adjacent external surfaces. HPRC is viewed as an alternative (or complementary) cooling technique to the use of pumped cryogenic or endothermic fuels to provide regenerative fuel or air cooling of the hot surfaces. The HPRC program has been conducted through two phases, an applications phase and a feasibility phase. The applications program (Phase 1) included concept and assessment analyses using hypersonic engine data obtained from US engine company contacts. The applications phase culminated with planning for experimental verification of the HPRC concept to be pursued in a feasibility program. The feasibility program (Phase 2), recently completed and summarized in this report, involved both analytical and experimental studies.

  6. DOE/JPL advanced thermionic technology program. Progress report No. 44, July, August, September 1980

    SciTech Connect (OSTI)

    Not Available

    1980-01-01T23:59:59.000Z

    The primary long-term goal of the DOE effort is to improve TEC performance to the level that thermionic topping of fossil fuel powerplants becomes technically possible and economically attractive. An intermediate goal is to demonstrate an in-boiler thermionic module in the early 1980's. A short-term goal is the demonstration of the reliability of thermionic operation in a combustion environment. The focus of the JPL program is to develop thermionic conversion technology appropriate for nuclear electric propulsion missions. These missions require operation at collector temperatures that are substantially higher than those associated with terrestrial applications. The DOE and JPL tasks for developing thermionic energy conversion are complementary and synergistic. Converter performance improvement is an area in which one agency's program supports the effort of the other. Significant accomplishments in this reporting period are described.

  7. Energy/National Nuclear Security Administration (NNSA) Career...

    Energy Savers [EERE]

    Graduates EnergyNational Nuclear Security Administration (NNSA) Career Pathways Program EnergyNational Nuclear Security Administration (NNSA) Career Pathways Program Intern...

  8. SPACE-R Thermionic Space Nuclear Power System: Design and Technology Demonstration Program. Semiannual technical progress report for period ending March 1993

    SciTech Connect (OSTI)

    Not Available

    1993-05-01T23:59:59.000Z

    This Semiannual Technical Progress Report summarizes the technical progress and accomplishments for the Thermionic Space Nuclear Power System (TI-SNPS) Design and Technology Demonstration Program of the Prime Contractor, Space Power Incorporated (SPI), its subcontractors and supporting National Laboratories during the first half of the Government Fiscal Year (GFY) 1993. SPI`s subcontractors and supporting National Laboratories include: Babcock & Wilcox for the reactor core and externals; Space Systems/Loral for the spacecraft integration; Thermocore for the radiator heat pipes and the heat exchanger; INERTEK of CIS for the TFE, core elements and nuclear tests; Argonne National Laboratories for nuclear safety, physics and control verification; and Oak Ridge National laboratories for materials testing. Parametric trade studies are near completion. However, technical input from INERTEK has yet to be provided to determine some of the baseline design configurations. The INERTEK subcontract is expected to be initiated soon. The Point Design task has been initiated. The thermionic fuel element (TFE) is undergoing several design iterations. The reactor core vessel analysis and design has also been started.

  9. Nuclear Engineering Student Learning Outcome Assessment Report

    E-Print Network [OSTI]

    Missouri-Rolla, University of

    1 Nuclear Engineering Student Learning Outcome Assessment Report 1. Program mission The Nuclear and graduate education to tomorrow's leaders in nuclear engineering. The program provides well-educated nuclear engineering professionals and leaders to Missouri and the nation in the commercial nuclear industry, national

  10. Nuclear Explosive Safety

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

    2009-04-14T23:59:59.000Z

    This Order establishes requirements to implement the nuclear explosive safety elements of DOE O 452.1D, Nuclear Explosive and Weapon Surety Program, for routine and planned nuclear explosive operations. Cancels DOE O 452.2C. Admin Chg 1, 7-10-13

  11. Nuclear Explosive Safety

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

    2009-04-14T23:59:59.000Z

    This Department of Energy (DOE) Order establishes requirements to implement the nuclear explosive safety (NES) elements of DOE O 452.1D, Nuclear Explosive and Weapon Surety Program, for routine and planned nuclear explosive operations (NEOs). Cancels DOE O 452.2C. Admin Chg 1, dated 7-10-13, cancels DOE O 452.2D.

  12. Performance and Controllability of Pulsed Ion Beam Ablation Propulsion

    SciTech Connect (OSTI)

    Yazawa, Masaru; Buttapeng, Chainarong; Harada, Nobuhiro [Nagaoka University of Technology, Department of Electrical Engineering, 1603-1 Kamitomioka, Nagaoka, Niigata 940-2188 (Japan); Suematsu, Hisayuki; Jiang Weihua; Yatsui, Kiyoshi [Nagaoka University of Technology, Extreme Energy-Density Research Institute, 1603-1 Kamitomioka, Nagaoka, Niigata 940-2188 (Japan)

    2006-05-02T23:59:59.000Z

    We propose novel propulsion driven by ablation plasma pressures produced by the irradiation of pulsed ion beams onto a propellant. The ion beam ablation propulsion demonstrates by a thin foil (50 {mu}mt), and the flyer velocity of 7.7 km/s at the ion beam energy density of 2 kJ/cm2 adopted by using the Time-of-flight method is observed numerically and experimentally. We estimate the performance of the ion beam ablation propulsion as specific impulse of 3600 s and impulse bit density of 1700 Ns/m2 obtained from the demonstration results. In the numerical analysis, a one-dimensional hydrodynamic model with ion beam energy depositions is used. The control of the ion beam kinetic energy is only improvement of the performance but also propellant consumption. The spacecraft driven by the ion beam ablation provides high performance efficiency with short-pulsed ion beam irradiation. The numerical results of the advanced model explained latent heat and real gas equation of state agreed well with experimental ones over a wide range of the incident ion beam energy density.

  13. Full fuel-cycle comparison of forklift propulsion systems.

    SciTech Connect (OSTI)

    Gaines, L. L.; Elgowainy, A.; Wang, M. Q.; Energy Systems

    2008-11-05T23:59:59.000Z

    Hydrogen has received considerable attention as an alternative to fossil fuels. The U.S. Department of Energy (DOE) investigates the technical and economic feasibility of promising new technologies, such as hydrogen fuel cells. A recent report for DOE identified three near-term markets for fuel cells: (1) Emergency power for state and local emergency response agencies, (2) Forklifts in warehousing and distribution centers, and (3) Airport ground support equipment markets. This report examines forklift propulsion systems and addresses the potential energy and environmental implications of substituting fuel-cell propulsion for existing technologies based on batteries and fossil fuels. Industry data and the Argonne Greenhouse Gases, Regulated Emissions, and Energy Use in Transportation (GREET) model are used to estimate full fuel-cycle emissions and use of primary energy sources, back to the primary feedstocks for fuel production. Also considered are other environmental concerns at work locations. The benefits derived from using fuel-cell propulsion are determined by the sources of electricity and hydrogen. In particular, fuel-cell forklifts using hydrogen made from the reforming of natural gas had lower impacts than those using hydrogen from electrolysis.

  14. Safety research programs sponsored by Office of Nuclear Regulatory Research: Progress report, October 1--December 31, 1987

    SciTech Connect (OSTI)

    Weiss, A.J. (comp.); Bari, R.A.; Boccio, J.L.; Fitzpatrick, R.; Ginsberg, T.; Greene, G.A.; Guppy, J.G.; Hall, R.E.; Higgins, J.C.; Khatib-Rahbar, M.

    1988-08-01T23:59:59.000Z

    The Advanced Reactor Review Safety Research Program has continued under NRC Research funding since October 1986. In April 1987, as a result of an NRC reorganization, the Accident Analysis and Safety Review of Liquid Metal and High Temperature Gas Reactors (LMRs and HTGRs) Program was transferred from Regulation to Research. Both programs are discussed here under the title of Accident Analysis and Safety Review of Liquid Metal and High Temperature Gas Reactors (LMRs and HTGRs). The combined programs are focused to help NRC accomplish the review of advanced reactor (LMR and HTGR) designs over the next year. Technical assistance in the following areas is provided: (1) review, adaptation, and implementation of analytical tools and models for application to the design submittals, (2) independent analysis of specific accidents and plant conditions and characteristics for the designs, (3) developing and evaluating appropriate source terms, (4) reviewing DOE reports on safety issues, (5) review of those aspects of DOE's base technical program related to the areas described in (1) through (4), and (6) assistance in assessing PRAs submitted for review.

  15. Worker Safety and Health Program for DOE (Including the National Nuclear Security Administration) Federal and Contractor Employees

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

    2011-10-20T23:59:59.000Z

    This document was developed to assist the Department of Energy (DOE or the Department) Federal and contractor employees in effectively developing, managing, and implementing a worker safety and health program. Cancels DOE G 440.1-1A and DOE G 440.1-8. Adm Chg 1, dated 3-22-13.

  16. Worker Safety and Health Program for DOE (Including the National Nuclear Security Administration) Federal and Contractor Employees

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

    2011-10-20T23:59:59.000Z

    This document was developed to assist the Department of Energy (DOE or the Department) Federal and contractor employees in effectively developing, managing, and implementing a worker safety and health program. Cancels DOE G 440.1-1A and DOE G 440.1-8. Adm Chg 1, dated 3-22-13, cancels DOE G 440.1-1B.

  17. Foreign programs for the storage of spent nuclear power plant fuels, high-level waste canisters and transuranic wastes

    SciTech Connect (OSTI)

    Harmon, K.M.; Johnson, A.B. Jr.

    1984-04-01T23:59:59.000Z

    The various national programs for developing and applying technology for the interim storage of spent fuel, high-level radioactive waste, and TRU wastes are summarized. Primary emphasis of the report is on dry storage techniques for uranium dioxide fuels, but data are also provided concerning pool storage.

  18. 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...

  19. Analysis of the LaSalle Unit 2 nuclear power plant: Risk Methods Integration and Evaluation Program (RMIEP). Volume 8, Seismic analysis

    SciTech Connect (OSTI)

    Wells, J.E.; Lappa, D.A.; Bernreuter, D.L.; Chen, J.C.; Chuang, T.Y. [Lawrence Livermore National Lab., CA (United States); Johnson, J.J.; Campbell, R.D.; Hashimoto, P.S.; Maslenikov, O.R.; Tiong, L.W.; Ravindra, M.K.; Kincaid, R.H. [EQE, International, Irvine, CA (United States); Sues, R.H.; Putcha, C.S. [NTS Engineering, Long Beach, CA (United States)

    1993-11-01T23:59:59.000Z

    This report describes the methodology used and the results obtained from the application of a simplified seismic risk methodology to the LaSalle County Nuclear Generating Station Unit 2. This study is part of the Level I analysis being performed by the Risk Methods Integration and Evaluation Program (RMIEP). Using the RMIEP developed event and fault trees, the analysis resulted in a seismically induced core damage frequency point estimate of 6.OE-7/yr. This result, combined with the component importance analysis, indicated that system failures were dominated by random events. The dominant components included diesel generator failures (failure to swing, failure to start, failure to run after started), and condensate storage tank.

  20. Structural Integrity Program for the 300,000-Gallon Radioactive Liquid Waste Storage Tanks at the Idaho Nuclear Technology and Engineering Center

    SciTech Connect (OSTI)

    Bryant, Jeffrey W.

    2010-08-12T23:59:59.000Z

    This report provides a record of the Structural Integrity Program for the 300,000-gal liquid waste storage tanks and associated equipment at the Idaho Nuclear Technology and Engineering Center, as required by U.S. Department of Energy M 435.1-1, Radioactive Waste Management Manual. This equipment is known collectively as the Tank Farm Facility. This report is an update, and replaces the previous report by the same title issued April 2003. The conclusion of this report is that the Tank Farm Facility tanks, vaults, and transfer systems that remain in service for storage are structurally adequate, and are expected to remain structurally adequate over the remainder of their planned service life through 2012. Recommendations are provided for continued monitoring of the Tank Farm Facility.

  1. Integrated null-flux suspension and multiphase propulsion system for magnetically-levitated vehicles

    DOE Patents [OSTI]

    Rote, D.M.; He, Jianliang; Johnson, L.R.

    1992-01-01T23:59:59.000Z

    This report discusses a propulsion and stabilization system comprising a series of figure 8 coils mounted vertically on the walls of the guideway to provide suspension, lateral guidance and propulsion of a magnetically levitated vehicle. This system further allows for altering the magnetic field effects by changing the relative position of the loops comprising the figure 8 coils either longitudinally and/or vertically with resulting changes in the propulsion, the vertical stability, and the suspension.

  2. Integrated null-flux suspension and multiphase propulsion system for magnetically-levitated vehicles

    DOE Patents [OSTI]

    Rote, D.M.; He, J.; Johnson, L.R.

    1994-01-04T23:59:59.000Z

    A propulsion and stabilization system are described comprising a series of coils mounted vertically on the walls of the guideway to provide suspension, lateral guidance, and propulsion of a magnetically levitated vehicle. This system further allows for altering the magnetic field effects by changing the relative position of the loops comprising the coils either longitudinally and/or vertically with resulting changes in the propulsion, the vertical stability, and the suspension. 8 figures.

  3. An Assessment of the Current Day Impact of Various Materials Associated with the U.S. Nuclear Test Program in the Marshall Island

    SciTech Connect (OSTI)

    Robison, W L; Noshkin, V E; Hamilton, T F; Conrado, C L; Bogen, K T

    2001-05-01T23:59:59.000Z

    Different stable elements, and some natural and man-made radionuclides, were used as tracers or associated in other ways with nuclear devices that were detonated at Bikini and Enewetak Atolls as part of the U.S. nuclear testing program from 1946 through 1958. The question has been raised whether any of these materials dispersed by the explosions could be of sufficient concentration in either the marine environment or on the coral islands to be of a health concern to people living, or planning to live, on the atolls. This report addresses that concern. An inventory of the materials involved during the test period was prepared and provided to us by the Office of Defense Programs (DP) of the United States Department of Energy (DOE). The materials that the DOE and the Republic of the Marshall Islands (RMI) ask to be evaluated are--sulfur, arsenic, yttrium, tantalum, gold, rhodium, indium, tungsten, thallium, thorium-230,232 ({sup 230,232}Th), uranium-233,238 ({sup 233,238}U), polonium-210 ({sup 210}Po), curium-232 ({sup 232}Cu), and americium-241 ({sup 241}Am). The stable elements were used primarily as tracers for determining neutron energy and flux, and for other diagnostic purposes in the larger yield, multistage devices. It is reasonable to assume that these materials would be distributed in a similar manner as the fission products subsequent to detonation. A large inventory of fission product and uranium data was available for assessment. Detailed calculations show only a very small fraction of the fission products produced during the entire test series remain at the test site atolls. Consequently, based on the information provided, we conclude that the concentration of these materials in the atoll environment pose no adverse health effects to humans.

  4. Risk-based Prioritization of Facility Decommissioning and Environmental Restoration Projects in the National Nuclear Legacy Liabilities Program at the Chalk River Laboratory - 13564

    SciTech Connect (OSTI)

    Nelson, Jerel G.; Kruzic, Michael [WorleyParsons, Mississauga, ON, L4W 4H2 (United States)] [WorleyParsons, Mississauga, ON, L4W 4H2 (United States); Castillo, Carlos [WorleyParsons, Las Vegas, NV 89128 (United States)] [WorleyParsons, Las Vegas, NV 89128 (United States); Pavey, Todd [WorleyParsons, Idaho Falls, ID 83402 (United States)] [WorleyParsons, Idaho Falls, ID 83402 (United States); Alexan, Tamer [WorleyParsons, Burnaby, BC, V5C 6S7 (United States)] [WorleyParsons, Burnaby, BC, V5C 6S7 (United States); Bainbridge, Ian [Atomic Energy Canada Limited, Chalk River Laboratories, Chalk River, ON, K0J1J0 (Canada)] [Atomic Energy Canada Limited, Chalk River Laboratories, Chalk River, ON, K0J1J0 (Canada)

    2013-07-01T23:59:59.000Z

    Chalk River Laboratory (CRL), located in Ontario Canada, has a large number of remediation projects currently in the Nuclear Legacy Liabilities Program (NLLP), including hundreds of facility decommissioning projects and over one hundred environmental remediation projects, all to be executed over the next 70 years. Atomic Energy of Canada Limited (AECL) utilized WorleyParsons to prioritize the NLLP projects at the CRL through a risk-based prioritization and ranking process, using the WorleyParsons Sequencing Unit Prioritization and Estimating Risk Model (SUPERmodel). The prioritization project made use of the SUPERmodel which has been previously used for other large-scale site prioritization and sequencing of facilities at nuclear laboratories in the United States. The process included development and vetting of risk parameter matrices as well as confirmation/validation of project risks. Detailed sensitivity studies were also conducted to understand the impacts that risk parameter weighting and scoring had on prioritization. The repeatable prioritization process yielded an objective, risk-based and technically defendable process for prioritization that gained concurrence from all stakeholders, including Natural Resources Canada (NRCan) who is responsible for the oversight of the NLLP. (authors)

  5. Operations of a Radioisotope-based Propulsion System Enabling CubeSat Exploration of the Outer Planets

    SciTech Connect (OSTI)

    Dr. Steven Howe; Nathan Jerred; Troy Howe; Adarsh Rajguru

    2014-05-01T23:59:59.000Z

    Exploration to the outer planets is an ongoing endeavor but in the current economical environment, cost reduction is the forefront of all concern. The success of small satellites such as CubeSats launched to Near-Earth Orbit has lead to examine their potential use to achieve cheaper science for deep space applications. However, to achieve lower cost missions; hardware, launch and operations costs must be minimized. Additionally, as we push towards smaller exploration beds with relative limited power sources, allowing for adequate communication back to Earth is imperative. Researchers at the Center for Space Nuclear Research are developing the potential of utilizing an advanced, radioisotope-based system. This system will be capable of providing both the propulsion power needed to reach the destination and the additional requirements needed to maintain communication while at location. Presented here are a basic trajectory analysis, communication link budget and concept of operations of a dual-mode (thermal and electric) radioisotope-based propulsion system, for a proposed mission to Enceladus (Saturnian icy moon) using a 6U CubeSat payload. The radioisotope system being proposed will be the integration of three sub-systems working together to achieve the overall mission. At the core of the system, stored thermal energy from radioisotope decay is transferred to a passing propellant to achieve high thrust useful for quick orbital maneuvering. An auxiliary closed-loop Brayton cycle can be operated in parallel to the thrusting mode to provide short bursts of high power for high data-rate communications back to Earth. Additionally, a thermal photovoltaic (TPV) energy conversion system will use radiation heat losses from the core. This in turn can provide the electrical energy needed to utilize the efficiency of ion propulsion to achieve quick interplanetary transit times. The intelligent operation to handle all functions of this system under optimized conditions adds to the complexity of the mission architecture.

  6. Analysis of Advanced Actinide-Fueled Energy Systems for Deep Space Propulsion Applications

    E-Print Network [OSTI]

    Guy, Troy Lamar

    2011-02-22T23:59:59.000Z

    [2]. Specific impulses on the order of 103 seconds are theoretically possible. Unfortunately, nuclear fusion ignition, confinement of hot dense plasma and extreme heat management continue to be enormous obstacles for even mid-term fusion.... In order to produce FF particles, a given fuel must fission with a high rate of probability, which is dependent on the energy of incident neutrons and target nuclei. The Java-based Nuclear Information Software (JANIS) program was used to prepare fission...

  7. High Fidelity Radiative Thermal Transport Simulations of a Scramjet Propulsion System.

    E-Print Network [OSTI]

    Irvine, Adam Glenn

    2013-01-01T23:59:59.000Z

    ??Scramjets are a type of air breathing propulsion system that have the potential to efficiently provide thrust for atmospheric vehicles at high speeds. Defining the (more)

  8. E-Print Network 3.0 - aircraft propulsion systems Sample Search...

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

    and Astronautics School of Engineering Summary: Aircraft Initiative, Robust Turbine Engine Design, Propulsion, Active Control of Aeromechanical Systems... an oxidizer, an...

  9. E-Print Network 3.0 - advanced propulsion concepts Sample Search...

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

    on the field emission principle... advanced technology in power conversion. The main advantages of a propulsion system based on the field emis... AS THRUSTERS FOR ELECTRIC SPACE...

  10. E-Print Network 3.0 - advanced electric propulsion Sample Search...

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

    Powered by Explorit Topic List Advanced Search Sample search results for: advanced electric propulsion Page: << < 1 2 3 4 5 > >> 1 Department of Aeronautics and Astronautics...

  11. E-Print Network 3.0 - advanced space propulsion Sample Search...

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

    Summary: for space drilling. The Jet Propulsion Laboratory's (JPL) ultrasonicsonic drillercorer (USDC... 1 Design and Modeling of the NU Smart Space Drilling System (SSDS)...

  12. E-Print Network 3.0 - advanced propulsion engine Sample Search...

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

    System Cleaner, smarter power for transit Summary: engine Propulsion power arrangement optimization & FC response Accessory loads, including balance... W Develop Fleet...

  13. Summer Undergraduate Research Opportunities in the Electric Propulsion and Plasmadynamics Laboratory (EPPDyL)*

    E-Print Network [OSTI]

    will then be detected using a mass spectrometer. Prior experience with basic electronic instruments is desirableSummer Undergraduate Research Opportunities in the Electric Propulsion and Plasmadynamics

  14. E-Print Network 3.0 - auxiliary propulsion applications Sample...

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

    MAE Seminar Series Combustion Chemistry and Laser Diagnostics for Aero-Propulsion and Energy... Applications Matthew A. Oehlschlaeger Rensselaer Polytechnic Institute Future...

  15. E-Print Network 3.0 - advanced embedded propulsion Sample Search...

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

    12;EPA Sensor... inserts 72 layer drift tube created72 layer drift tube created 12;MicroMicro--Propulsion ... Source: Boise State University, Center for...

  16. New Solicitations | National Nuclear Security Administration

    National Nuclear Security Administration (NNSA)

    National Laser Users' Facility Grant Program New Solicitations New Solicitations National Laser Users' Facility Grant Program New Solicitations The National Nuclear Security...

  17. Final Technical Report; NUCLEAR ENGINEERING RECRUITMENT EFFORT

    SciTech Connect (OSTI)

    Kerrick, Sharon S.; Vincent, Charles D.

    2007-07-02T23:59:59.000Z

    This report provides the summary of a project whose purpose was to support the costs of developing a nuclear engineering awareness program, an instruction program for teachers to integrate lessons on nuclear science and technology into their existing curricula, and web sites for the exchange of nuclear engineering career information and classroom materials. The specific objectives of the program were as follows: OBJECTIVE 1: INCREASE AWARENESS AND INTEREST OF NUCLEAR ENGINEERING; OBJECTIVE 2: INSTRUCT TEACHERS ON NUCLEAR TOPICS; OBJECTIVE 3: NUCLEAR EDUCATION PROGRAMS WEB-SITE; OBJECTIVE 4: SUPPORT TO UNIVERSITY/INDUSTRY MATCHING GRANTS AND REACTOR SHARING; OBJECTIVE 5: PILOT PROJECT; OBJECTIVE 6: NUCLEAR ENGINEERING ENROLLMENT SURVEY AT UNIVERSITIES

  18. YALINA facility a sub-critical Accelerator- Driven System (ADS) for nuclear energy research facility description and an overview of the research program (1997-2008).

    SciTech Connect (OSTI)

    Gohar, Y.; Smith, D. L.; Nuclear Engineering Division

    2010-04-28T23:59:59.000Z

    The YALINA facility is a zero-power, sub-critical assembly driven by a conventional neutron generator. It was conceived, constructed, and put into operation at the Radiation Physics and Chemistry Problems Institute of the National Academy of Sciences of Belarus located in Minsk-Sosny, Belarus. This facility was conceived for the purpose of investigating the static and dynamic neutronics properties of accelerator driven sub-critical systems, and to serve as a neutron source for investigating the properties of nuclear reactions, in particular transmutation reactions involving minor-actinide nuclei. This report provides a detailed description of this facility and documents the progress of research carried out there during a period of approximately a decade since the facility was conceived and built until the end of 2008. During its history of development and operation to date (1997-2008), the YALINA facility has hosted several foreign groups that worked with the resident staff as collaborators. The participation of Argonne National Laboratory in the YALINA research programs commenced in 2005. For obvious reasons, special emphasis is placed in this report on the work at YALINA facility that has involved Argonne's participation. Attention is given here to the experimental program at YALINA facility as well as to analytical investigations aimed at validating codes and computational procedures and at providing a better understanding of the physics and operational behavior of the YALINA facility in particular, and ADS systems in general, during the period 1997-2008.

  19. Phase 1 Space Fission Propulsion Energy Source Design

    SciTech Connect (OSTI)

    Houts, Mike; Van Dyke, Melissa; Godfroy, Tom; Pedersen, Kevin; Martin, James; Dickens, Ricky; Salvail, Pat; Hrbud, Ivana; Carter, Robert [NASA MSFC, TD40, Marshall Space Flight Center, Alabama, 35812 (United States)

    2002-07-01T23:59:59.000Z

    Fission technology can enable rapid, affordable access to any point in the solar system. If fission propulsion systems are to be developed to their full potential; however, near-term customers must be identified and initial fission systems successfully developed, launched, and operated. Studies conducted in fiscal year 2001 (IISTP, 2001) show that fission electric propulsion (FEP) systems with a specific mass at or below 50 kg/kWjet could enhance or enable numerous robotic outer solar system missions of interest. At the required specific mass, it is possible to develop safe, affordable systems that meet mission requirements. To help select the system design to pursue, eight evaluation criteria were identified: system integration, safety, reliability, testability, specific mass, cost, schedule, and programmatic risk. A top-level comparison of four potential concepts was performed: a Testable, Passive, Redundant Reactor (TPRR), a Testable Multi-Cell In-Core Thermionic Reactor (TMCT), a Direct Gas Cooled Reactor (DGCR), and a Pumped Liquid Metal Reactor (PLMR). Development of any of the four systems appears feasible. However, for power levels up to at least 500 kWt (enabling electric power levels of 125-175 kWe, given 25-35% power conversion efficiency) the TPRR has advantages related to several criteria and is competitive with respect to all. Hardware-based research and development has further increased confidence in the TPRR approach. Successful development and utilization of a 'Phase 1' fission electric propulsion system will enable advanced Phase 2 and Phase 3 systems capable of providing rapid, affordable access to any point in the solar system. (authors)

  20. ADVANCED RADIOISOTOPE HEAT SOURCE AND PROPULSION SYSTEMS FOR PLANETARY EXPLORATION

    SciTech Connect (OSTI)

    R. C. O'Brien; S. D. Howe; J. E. Werner

    2010-09-01T23:59:59.000Z

    The exploration of planetary surfaces and atmospheres may be enhanced by increasing the range and mobility of a science platform. Fundamentally, power production and availability of resources are limiting factors that must be considered for all science and exploration missions. A novel power and propulsion system is considered and discussed with reference to a long-range Mars surface exploration mission with in-situ resource utilization. Significance to applications such as sample return missions is also considered. Key material selections for radioisotope encapsulation techniques are presented.

  1. The Use of Steady and Pulsed Detonations for Propulsion Systems

    SciTech Connect (OSTI)

    Adelman, H.G.; Menees, G.P.; Cambier, J.L.; Bowles, J.V.

    1996-02-01T23:59:59.000Z

    Objectives of the ODWE concept studies are: demonstrate the feasibility of the oblique detonation wave engine (ODWE) for hypersonic propulsion; demonstrate the existance and stability of an oblique detonation wave in hypersonic wind tunnels; develop engineering codes which predict the performance characteristics of the ODWE including specific impulse and thrust coefficients for various operating conditions; develop multi-dimensional computer codes which can model all aspects of the ODWE including fuel injection, mixing, ignition, combustion and expansion with fully detailed chemical kinetics and turbulence models; and validate the codes with experimental data use the simulations to predict the ODWE performance for conditions not easily obtained in wind tunnels.

  2. Opening up the future in space with nuclear power

    SciTech Connect (OSTI)

    Buden, D.; Angelo, J. Jr.

    1985-01-01T23:59:59.000Z

    Man's extraterrestrial development is dependent on abundant power. For example, space-based manufacturing facilities are projected to have a power demand of 300 kWe by the end of this Century, and several megawatts in the early part of next millennium. The development of the lunar resource base will result in power needs ranging from an initial 100 kW(e) to many megawatts. Human visits to Mars could be achieved using a multimegawatt nuclear electric propulsion system or high thrust nuclear rockets. Detailed exploration of the solar system will also be greatly enhanced by the availability of large nuclear electric propulsion systems. All of these activities will require substantial increases in space power - hundreds of kilowatts to many megawatts. The challenge is clear: how to effectively use nuclear energy to support humanity's expansion into space.

  3. RADIOISOTOPE-DRIVEN DUAL-MODE PROPULSION SYSTEM FOR CUBESAT-SCALE PAYLOADS TO THE OUTER PLANETS

    SciTech Connect (OSTI)

    N. D. Jerred; T. M. Howe; S. D. Howe; A. Rajguru

    2014-02-01T23:59:59.000Z

    It is apparent the cost of planetary exploration is rising as mission budgets declining. Currently small scientific beds geared to performing limited tasks are being developed and launched into low earth orbit (LEO) in the form of small-scale satellite units, i.e., CubeSats. These micro- and nano-satellites are gaining popularity among the university and science communities due to their relatively low cost and design flexibility. To date these small units have been limited to performing tasks in LEO utilizing solar-based power. If a reasonable propulsion system could be developed, these CubeSat platforms could perform exploration of various extra-terrestrial bodies within the solar system engaging a broader range of researchers. Additionally, being mindful of mass, smaller cheaper launch vehicles (approximately 1,000 kgs to LEO) can be targeted. Thus, in effect, allows for beneficial exploration to be conducted within limited budgets. Researchers at the Center for Space Nuclear Research (CSNR) are proposing a low mass, radioisotope-based, dual-mode propulsion system capable of extending the exploration realm of these CubeSats out of LEO.

  4. Department of Energy Programmatic Spent Nuclear Fuel Management and Idaho National Engineering Laboratory Environmental Restoration and Waste Management Programs Draft Environmental Impact Statement; Volume 1, Appendix F, Nevada Test Site and Oak Ridge Reservation Spent Nuclear Fuel Management Programs

    SciTech Connect (OSTI)

    NONE

    1994-06-01T23:59:59.000Z

    This volume addresses the interim storage of spent nuclear fuel (SNF) at two US Department of Energy sites, the Nevada Test Site (NTS) and the Oak Ridge Reservation (ORR). These sites are being considered to provide a reasonable range of alternative settings at which future SNF management activities could be conducted. These locations are not currently involved in management of large quantities of SNF; NTS has none, and ORR has only small quantities. But NTS and ORR do offer experience and infrastructure for the handling, processing and storage of radioactive materials, and they do exemplify a broad spectrum of environmental parameters. This broad spectrum of environmental parameters will provide, a perspective on whether and how such location attributes may relate to potential environmental impacts. Consideration of these two sites will permit a programmatic decision to be based upon an assessment of the feasible options without bias, to the current storage sites. This volume is divided into four parts. Part One is the volume introduction. Part Two contains chapters one through five for the NTS, as well as references contained in chapter six. Part Three contains chapters one through five for the ORR, as well as references contained in chapter six. Part Four is summary information including the list of preparers, organizations contacted, acronyms, and abbreviations for both the NTS and the ORR. A Table of Contents, List of Figures, and List of Tables are included in parts Two, Three, and Four. This approach permitted the inclusion of both sites in one volume while maintaining consistent chapter numbering.

  5. Item No. 3 process facilities cost estimates and schedules for facilities capability assurance program nuclear facilities modernization - FY 1989 line item, authorization No. D79

    SciTech Connect (OSTI)

    NONE

    1989-07-01T23:59:59.000Z

    Data is presented concerning cost estimates and schedules for process facilities and nuclear facilities modernization.

  6. Radioisotope Electric Propulsion for Deep Space Sample Return

    SciTech Connect (OSTI)

    Noble, Robert J.; /SLAC

    2009-07-14T23:59:59.000Z

    The need to answer basic questions regarding the origin of the Solar System will motivate robotic sample return missions to destinations like Pluto, its satellite Charon, and objects in the Kuiper belt. To keep the mission duration short enough to be of interest, sample return from objects farther out in the Solar System requires increasingly higher return velocities. A sample return mission involves several complicated steps to reach an object and obtain a sample, but only the interplanetary return phase of the mission is addressed in this paper. Radioisotope electric propulsion is explored in this parametric study as a means to propel small, dedicated return vehicles for transferring kilogram-size samples from deep space to Earth. Return times for both Earth orbital rendezvous and faster, direct atmospheric re-entry trajectories are calculated for objects as far away as 100 AU. Chemical retro-rocket braking at Earth is compared to radioisotope electric propulsion but the limited deceleration capability of chemical rockets forces the return trajectories to be much slower.

  7. Hydrodynamic Efficiency of Ablation Propulsion with Pulsed Ion Beam

    SciTech Connect (OSTI)

    Buttapeng, Chainarong; Yazawa, Masaru; Harada, Nobuhiro [Department of Electrical Engineering, Nagaoka University of Technology, 1603-1, Kamitomioka, Nagaoka 940-2188 (Japan); Suematsu, Hisayuki; Jiang Weihua; Yatsui, Kiyoshi [Extreme Energy-Density Research Institute, Nagaoka University of Technology, 1603-1, Kamitomioka, Nagaoka 940-2188 (Japan)

    2006-05-02T23:59:59.000Z

    This paper presents the hydrodynamic efficiency of ablation plasma produced by pulsed ion beam on the basis of the ion beam-target interaction. We used a one-dimensional hydrodynamic fluid compressible to study the physics involved namely an ablation acceleration behavior and analyzed it as a rocketlike model in order to investigate its hydrodynamic variables for propulsion applications. These variables were estimated by the concept of ablation driven implosion in terms of ablated mass fraction, implosion efficiency, and hydrodynamic energy conversion. Herein, the energy conversion efficiency of 17.5% was achieved. In addition, the results show maximum energy efficiency of the ablation process (ablation efficiency) of 67% meaning the efficiency with which pulsed ion beam energy-ablation plasma conversion. The effects of ion beam energy deposition depth to hydrodynamic efficiency were briefly discussed. Further, an evaluation of propulsive force with high specific impulse of 4000s, total impulse of 34mN and momentum to energy ratio in the range of {mu}N/W was also analyzed.

  8. Beamed Core Antimatter Propulsion: Engine Design and Optimization

    E-Print Network [OSTI]

    Ronan Keane; Wei-Ming Zhang

    2012-05-16T23:59:59.000Z

    A conceptual design for beamed core antimatter propulsion is reported, where electrically charged annihilation products directly generate thrust after being deflected and collimated by a magnetic nozzle. Simulations were carried out using the Geant4 (Geometry and tracking) software toolkit released by the CERN accelerator laboratory for Monte Carlo simulation of the interaction of particles with matter and fields. Geant permits a more sophisticated and comprehensive design and optimization of antimatter engines than the software environment for simulations reported by prior researchers. The main finding is that effective exhaust speeds Ve ~ 0.69c (where c is the speed of light) are feasible for charged pions in beamed core propulsion, a major improvement over the Ve ~ 0.33c estimate based on prior simulations. The improvement resulted from optimization of the geometry and the field configuration of the magnetic nozzle. Moreover, this improved performance is realized using a magnetic field on the order of 10 T at the location of its highest magnitude. Such a field could be produced with today's technology, whereas prior nozzle designs anticipated and required major advances in this area. The paper also briefly reviews prospects for production of the fuel needed for a beamed core engine.

  9. RESEARCH TRAINING GROUP GRK 1095/1: "AERO-THERMODYNAMIC DESIGN OF A SCRAMJET PROPULSION SYSTEM"

    E-Print Network [OSTI]

    RESEARCH TRAINING GROUP GRK 1095/1: "AERO-THERMODYNAMIC DESIGN OF A SCRAMJET PROPULSION SYSTEM" U conception. In this context only the use of a scramjet-propulsion system meets all the aerodynamic it must be mentioned that scramjet-technologies are one of the key technologies for hypersonic flight

  10. The 32nd International Electric Propulsion Conference, Wiesbaden, Germany September 11 15, 2011

    E-Print Network [OSTI]

    The 32nd International Electric Propulsion Conference, Wiesbaden, Germany September 11 ­ 15, 2011 1 Electric Propulsion Conference, Wiesbaden · Germany September 11 ­ 15, 2011 K. Matyash1 , Max-Planck-Institut für Plasmaphysik, EURATOM Association, Greifswald, D-17491, Germany R. Schneider2 , Greifswald

  11. Design and Control of the Induction Motor Propulsion of an Electric Vehicle

    E-Print Network [OSTI]

    Brest, Université de

    Design and Control of the Induction Motor Propulsion of an Electric Vehicle B. Tabbache1,2 , A for presizing the induction motor propulsion of an Electric Vehicle (EV). Based on the EV desired performances for different induction motor-based EVs using a siding mode control technique. Index Terms--Electric Vehicle (EV

  12. An Exoskeleton Using Controlled Energy Storage and Release to Aid Ankle Propulsion

    E-Print Network [OSTI]

    Collins, Steven H.

    An Exoskeleton Using Controlled Energy Storage and Release to Aid Ankle Propulsion M. Bruce Wiggin Mellon University Pittsburgh, PA, USA Abstract -- Symmetric ankle propulsion is the cornerstone of efficient human walking. The ankle plantar flexors provide the majority of the mechanical work for the step

  13. The 33st International Electric Propulsion Conference, The George Washington University, USA October 6 10, 2013

    E-Print Network [OSTI]

    Walker, Mitchell

    The 33st International Electric Propulsion Conference, The George Washington University, USA, 30332, USA Abstract: Accurate measurement of ion charge flux in the plume of spacecraft electric.walker@ae.gatech.edu #12;The 33st International Electric Propulsion Conference, The George Washington University, USA

  14. Magnetic Propulsion of Intense Lithium Streams in a Tokamak Magnetic Field

    E-Print Network [OSTI]

    Zakharov, Leonid E.

    Magnetic Propulsion of Intense Lithium Streams in a Tokamak Magnetic Field Leonid E. Zakharov the theory of magnetic propulsion of liquid lithium streams and their stability in tokamaks and other interactions with the magnetic #12;eld. A criterion is obtained for stabilization of the \\sausage

  15. Design, fabrication and analysis of a body-caudal fin propulsion system for a microrobotic fish

    E-Print Network [OSTI]

    Wood, Robert

    Design, fabrication and analysis of a body-caudal fin propulsion system for a microrobotic fish Kyu and fabrica- tion of a centimeter-scale propulsion system for a robotic fish. The key to the design are customized to provide the necessary work output for the microrobotic fish. The flexure joints, electrical

  16. Nuclear Energy Papers and Presentations

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

    PapersPresentations View Nuclear Energy papers & presentations. Skip Navigation Links Home Newsroom About INL Careers Research Programs Energy and Environment National and...

  17. Federal Technical Capability Program (FTCP) | Department of Energy

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

    Illness Compensation Program Pamphlet Federal Technical Capability Program (FTCP) Accident Investigation Reports Nuclear Safety Facility Safety Security Classification...

  18. Preserving Nuclear Grade Knowledge

    SciTech Connect (OSTI)

    Lange, Bob

    2008-02-05T23:59:59.000Z

    When people think of the government they think of the President, or Congress, or the Internal Revenue Service (IRS), but there are thousands of people in government-related jobs doing things most dont really notice everyday. You can find them everywhere, from the space science folks at NASA, to the Federal Bureau of Investigations (FBI) watching out for the bad guys. There are Rangers, and Social Workers, Nurses and Agricultural Managers. They are people working to keep the many facets of the USA rolling. One very diverse bunch is The Department of Energy (DOE) , a group who is expanding the ways we make and save energy to power our cars, homes, and businesses. Tucked away under the DOE is the National Nuclear Security Administration, the NNSA is an agency that maintains the safety, security, and reliability of the U.S. nuclear weapons stockpile. It works to reduce global danger from weapons of mass destruction. It provides the U.S. Navy with safe nuclear propulsion, and it responds to nuclear and radiological emergencies in the United States and abroad, and it supports efforts in science and technology*. (* DOE/NNSA/KCP website info)

  19. Nuclear Nonproliferation Program Offices | National Nuclear Security

    National Nuclear Security Administration (NNSA)

    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) "ofEarlyEnergyDepartmentNationalRestart of the Review of the Yucca0AdministrationNext100

  20. Deuterium-Tritium Pulse Propulsion with Hydrogen as Propellant and the Entire Spacecraft as a Gigavolt Capacitor for Ignition

    E-Print Network [OSTI]

    Winterberg, Friedwardt

    2012-01-01T23:59:59.000Z

    A deuterium-tritium (DT) nuclear pulse propulsion concept for fast interplanetary transport is proposed utilizing almost all the energy for thrust and without the need for a large radiator: 1. By letting the thermonuclear micro-explosion take place in the center of a liquid hydrogen sphere with the radius of the sphere large enough to slow down and absorb the neutrons of the DT fusion reaction, heating the hydrogen to a fully ionized plasma at a temperature of ~ 105 K. 2. By using the entire spacecraft as a magnetically insulated gigavolt capacitor, igniting the DT micro-explosion with an intense GeV ion beam discharging the gigavolt capacitor, possible if the space craft has the topology of a torus.

  1. Deuterium-Tritium Pulse Propulsion with Hydrogen as Propellant and the Entire Spacecraft as a Gigavolt Capacitor for Ignition

    E-Print Network [OSTI]

    Friedwardt Winterberg

    2012-07-31T23:59:59.000Z

    A deuterium-tritium (DT) nuclear pulse propulsion concept for fast interplanetary transport is proposed utilizing almost all the energy for thrust and without the need for a large radiator: 1. By letting the thermonuclear micro-explosion take place in the center of a liquid hydrogen sphere with the radius of the sphere large enough to slow down and absorb the neutrons of the DT fusion reaction, heating the hydrogen to a fully ionized plasma at a temperature of ~ 105 K. 2. By using the entire spacecraft as a magnetically insulated gigavolt capacitor, igniting the DT micro-explosion with an intense GeV ion beam discharging the gigavolt capacitor, possible if the space craft has the topology of a torus.

  2. The Off-Site Plowshare and Vela Uniform Programs: Assessing Potential Environmental Liabilities through an Examination of Proposed Nuclear Projects,High Explosive Experiments, and High Explosive Construction Activities Volume 2 of 3

    SciTech Connect (OSTI)

    Beck Colleen M.,Edwards Susan R.,King Maureen L.

    2011-09-01T23:59:59.000Z

    This document presents the results of nearly six years (2002-2008) of historical research and field studies concerned with evaluating potential environmental liabilities associated with U.S. Atomic Energy Commission projects from the Plowshare and Vela Uniform Programs. The Plowshare Program's primary purpose was to develop peaceful uses for nuclear explosives. The Vela Uniform Program focused on improving the capability of detecting, monitoring and identifying underground nuclear detonations. As a result of the Project Chariot site restoration efforts in the early 1990s, there were concerns that there might be other project locations with potential environmental liabilities. The Desert Research Institute conducted archival research to identify projects, an analysis of project field activities, and completed field studies at locations where substantial fieldwork had been undertaken for the projects. Although the Plowshare and Vela Uniform nuclear projects are well known, the projects that are included in this research are relatively unknown. They are proposed nuclear projects that were not executed, proposed and executed high explosive experiments, and proposed and executed high explosive construction activities off the Nevada Test Site. The research identified 170 Plowshare and Vela Uniform off-site projects and many of these had little or no field activity associated with them. However, there were 27 projects that merited further investigation and field studies were conducted at 15 locations.

  3. The Off-Site Plowshare and Vela Uniform Programs: Assessing Potential Environmental Liabilities through an Examination of Proposed Nuclear Projects,High Explosive Experiments, and High Explosive Construction Activities Volume 3 of 3

    SciTech Connect (OSTI)

    Beck Colleen M.,Edwards Susan R.,King Maureen L.

    2011-09-01T23:59:59.000Z

    This document presents the results of nearly six years (2002-2008) of historical research and field studies concerned with evaluating potential environmental liabilities associated with U.S. Atomic Energy Commission projects from the Plowshare and Vela Uniform Programs. The Plowshare Program's primary purpose was to develop peaceful uses for nuclear explosives. The Vela Uniform Program focused on improving the capability of detecting, monitoring and identifying underground nuclear detonations. As a result of the Project Chariot site restoration efforts in the early 1990s, there were concerns that there might be other project locations with potential environmental liabilities. The Desert Research Institute conducted archival research to identify projects, an analysis of project field activities, and completed field studies at locations where substantial fieldwork had been undertaken for the projects. Although the Plowshare and Vela Uniform nuclear projects are well known, the projects that are included in this research are relatively unknown. They are proposed nuclear projects that were not executed, proposed and executed high explosive experiments, and proposed and executed high explosive construction activities off the Nevada Test Site. The research identified 170 Plowshare and Vela Uniform off-site projects and many of these had little or no field activity associated with them. However, there were 27 projects that merited further investigation and field studies were conducted at 15 locations.

  4. The Off-Site Plowshare and Vela Uniform Programs: Assessing Potential Environmental Liabilities through an Examination of Proposed Nuclear Projects,High Explosive Experiments, and High Explosive Construction Activities Volume 1 of 3

    SciTech Connect (OSTI)

    Beck Colleen M,Edwards Susan R.,King Maureen L.

    2011-09-01T23:59:59.000Z

    This document presents the results of nearly six years (2002-2008) of historical research and field studies concerned with evaluating potential environmental liabilities associated with U.S. Atomic Energy Commission projects from the Plowshare and Vela Uniform Programs. The Plowshare Program's primary purpose was to develop peaceful uses for nuclear explosives. The Vela Uniform Program focused on improving the capability of detecting, monitoring and identifying underground nuclear detonations. As a result of the Project Chariot site restoration efforts in the early 1990s, there were concerns that there might be other project locations with potential environmental liabilities. The Desert Research Institute conducted archival research to identify projects, an analysis of project field activities, and completed field studies at locations where substantial fieldwork had been undertaken for the projects. Although the Plowshare and Vela Uniform nuclear projects are well known, the projects that are included in this research are relatively unknown. They are proposed nuclear projects that were not executed, proposed and executed high explosive experiments, and proposed and executed high explosive construction activities off the Nevada Test Site. The research identified 170 Plowshare and Vela Uniform off-site projects and many of these had little or no field activity associated with them. However, there were 27 projects that merited further investigation and field studies were conducted at 15 locations.

  5. Department of Energy Programmatic Spent Nuclear Fuel Management and Idaho National Engineering Laboratory Environmental Restoration and Waste Management Programs Draft Environmental Impact Statement. Volume 1, Appendix D, Part B: Naval spent nuclear fuel management

    SciTech Connect (OSTI)

    Not Available

    1994-06-01T23:59:59.000Z

    This volume contains the following attachments: transportation of Naval spent nuclear fuel; description of Naval spent nuclear receipt and handling at the Expended Core Facility at the Idaho National Engineering Laboratory; comparison of storage in new water pools versus dry container storage; description of storage of Naval spent nuclear fuel at servicing locations; description of receipt, handling, and examination of Naval spent nuclear fuel at alternate DOE facilities; analysis of normal operations and accident conditions; and comparison of the Naval spent nuclear fuel storage environmental assessment and this environmental impact statement.

  6. Nuclear Explosive Safety

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

    2006-06-12T23:59:59.000Z

    The directive establishes specific nuclear explosive safety (NES) program requirements to implement the DOE NES standards and other NES criteria for routine and planned nuclear explosive operations. Cancels DOE O 452.2B. Canceled by DOE O 452.2D.

  7. Lithium/iron sulfide batteries for electric-vehicle propulsion and other applications. Progress report, October 1979-March 1980

    SciTech Connect (OSTI)

    None

    1980-08-01T23:59:59.000Z

    The research and development activities of the program at Argonne National Laboratory (ANL) on lithium/iron sulfide batteries during the period October 1979-March 1980 is described. Although the major emphasis is currently on batteries for electric-vehicle propulsion, stationary energy-storage applications are also under investigation. The individual battery cells, which operate at 400 to 500/sup 0/C, are of a vertically oriented, prismatic design with two or more positive electrodes of FeS or FeS/sub 2/, facing negative electrodes of lithium-aluminum or lithium-silicon alloy, and molten LiCl-KCl electrolyte. The ANL program consists of cell chemistry studies, materials engineering, and component and auxiliary systems development. Important elements of this program are studies of the effects of design modifications on cell performance and post-test examinations of cells. During the reporting period, cell and battery development work has been aimed primarily at the first phase of the Mark II electric-vehicle battery program, which consists of an effort to develop high-reliability cells having boron nitride felt separators. Later in the Mark II program, the cells will be tested in 10-cell modules. Work on stationary energy-storage batteries during this period has consisted mainly of conceptual design studies. 23 figures, 9 tables.

  8. Nuclear Science Division, Annual report, October 1, 1988--December 31, 1990

    SciTech Connect (OSTI)

    Poskanzer, A.M.; Deleplanque, M.A.; Firestone, R.B.; Lofdahl, J.B. (eds.)

    1991-04-01T23:59:59.000Z

    This report contains short papers of research conducted in the following areas: Low energy research program; bevalac research program; ultrarelativistic research program; nuclear theory program; nuclear data evaluation; and, 88-inch cyclotron operations.

  9. Feasibility study of a nonequilibrium MHD accelerator concept for hypersonic propulsion ground testing

    SciTech Connect (OSTI)

    Lee, Ying-Ming; Simmons, G.A.; Nelson, G.L. [MSE Inc., Butte, MT (United States)

    1995-12-31T23:59:59.000Z

    A National Aeronautics and Space Administration (NASA) funded research study to evaluate the feasibility of using magnetohydrodynamic (MHD) body force accelerators to produce true air simulation for hypersonic propulsion ground testing is discussed in this paper. Testing over the airbreathing portion of a transatmospheric vehicle (TAV) hypersonic flight regime will require high quality air simulation for actual flight conditions behind a bow shock wave (forebody, pre-inlet region) for flight velocities up to Mach 16 and perhaps beyond. Material limits and chemical dissociation at high temperature limit the simulated flight Mach numbers in conventional facilities to less than Mach 12 for continuous and semi-continuous testing and less than Mach 7 for applications requiring true air chemistry. By adding kinetic energy directly to the flow, MHD accelerators avoid the high temperatures and pressures required in the reservoir region of conventional expansion facilities, allowing MHD to produce true flight conditions in flight regimes impossible with conventional facilities. The present study is intended to resolve some of the critical technical issues related to the operation of MHD at high pressure. Funding has been provided only for the first phase of a three to four year feasibility study that would culminate in the demonstration of MHD acceleration under conditions required to produce true flight conditions behind a bow shock wave to flight Mach numbers of 16 or greater. MHD critical issues and a program plan to resolve these are discussed.

  10. DUAL-MODE PROPULSION SYSTEM ENABLING CUBESAT EXPLORATION OF THE SOLAR SYSTEM NASA Innovative Advanced Concepts (NIAC) Phase I Final Report

    SciTech Connect (OSTI)

    Nathan Jerred; Troy Howe; Adarsh Rajguru; Dr. Steven Howe

    2014-06-01T23:59:59.000Z

    It is apparent the cost of planetary exploration is rising as mission budgets declining. Currently small scientific beds geared to performing limited tasks are being developed and launched into low earth orbit (LEO) in the form of small-scale satellite units, i.e., CubeSats. These micro- and nano-satellites are gaining popularity among the university and science communities due to their relatively low cost and design flexibility. To date these small units have been limited to performing tasks in LEO utilizing solar-based power. If a reasonable propulsion system could be developed, these CubeSat platforms could perform exploration of various extra-terrestrial bodies within the solar system engaging a broader range of researchers. Additionally, being mindful of mass, smaller cheaper launch vehicles (~1,000 kgs to LEO) can be targeted. This, in effect, allows for beneficial explora-tion to be conducted within limited budgets. Researchers at the Center for Space Nuclear Re-search (CSNR) are proposing a low mass, radioisotope-based, dual-mode propulsion system capable of extending the exploration realm of these CubeSats out of LEO. The proposed radioisotope-based system would leverage the high specific energies [J/kg] associated with radioisotope materials and enhance their inherent low specific powers [W/g]. This is accomplished by accumulating thermal energy from nuclear decay within a central core over time. This allows for significant amounts of power to be transferred to a flowing gas over short periods of time. In the proposed configuration the stored energy can be utilized in two ways: (1) with direct propellant injection to the core, the energy can be converted into thrust through the use of a converging-diverging nozzle and (2) by flowing a working fluid through the core and subsequent Brayton engine, energy within the core can be converted to electrical energy. The first scenario achieves moderate ranges of thrust, but at a higher Isp than traditional chemical-based systems. The second scenario allows for the production of electrical power, which is then available for electric-based propulsion. Additionally, once at location the production of electrical power can be dedicated to the payloads communication system for data transfer. Ultimately, the proposed dual-mode propulsion platform capitalizes on the benefits of two types of propulsion methods the thrust of thermal propulsion ideal for quick orbital maneuvers and the specific impulse of electric propulsion ideal for efficient inter-planetary travel. Previous versions of this RTR-based concept have been studied for various applications [NETS 1-3]. The current version of this concept is being matured through a NASA Innovative Advanced Concepts (NIAC) Phase I grant, awarded for FY 2014. In this study the RTR concept is being developed to deliver a 6U CubeSat payload to the orbit of the Saturnian moon - Enceladus. Additionally, this study will develop an entire mission architecture for Enceladus targeting a total allowable launch mass of 1,000 kg.

  11. Nuclear Engineering A Guide for

    E-Print Network [OSTI]

    Schulte, Mike

    Nuclear Engineering A Guide for Undergraduate Majors Last modified Fall 2014 This guide applies-7451, Internet: www.engr.wisc.edu/ep/ #12;1 Introduction The Nuclear Engineering Program is administered to provide Nuclear Engineering undergraduate students with information that will facilitate their studies

  12. 2011 NMMSS Users Training Meeting | National Nuclear Security...

    National Nuclear Security Administration (NNSA)

    Working at NNSA Blog Home About Us Our Programs Defense Nuclear Security Nuclear Materials Management & Safeguards System Training Annual Users Training Meeting...

  13. 2009 NMMSS Users Training Meeting | National Nuclear Security...

    National Nuclear Security Administration (NNSA)

    Working at NNSA Blog Home About Us Our Programs Defense Nuclear Security Nuclear Materials Management & Safeguards System Training Annual Users Training Meeting...

  14. 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...

  15. National Nuclear Data Center Nuclear Data Portal www.nndc.bnl.gov

    E-Print Network [OSTI]

    Ohta, Shigemi

    National Nuclear Data Center #12;Nuclear Data Portal www.nndc.bnl.gov Nuclear Data Portal New generation of nuclear data services, using modern and powerful DELL servers, Sybase relational database software, Linux operating system, and Java programming language. The Portal includes nuclear structure

  16. An impulse framework for hydrodynamic force analysis : fish propulsion, water entry of spheres, and marine propellers

    E-Print Network [OSTI]

    Epps, Brenden P

    2010-01-01T23:59:59.000Z

    This thesis presents an impulse framework for analyzing the hydrodynamic forces on bodies in flow. This general theoretical framework is widely applicable, and it is used to address the hydrodynamics of fish propulsion, ...

  17. Submarine propulsion shaft life : probabilistic prediction and extension through prevention of water ingress

    E-Print Network [OSTI]

    Jonart, Douglas E. (Douglas Edward)

    2014-01-01T23:59:59.000Z

    Submarine propulsion shafts have demonstrated acceptable reliability performance when inspected and refurbished at least every 6 years. Designers wish to extend the inspection interval to 12 years without sacrificing ...

  18. A fully microfabricated two-dimensional electrospray array with applications to space propulsion

    E-Print Network [OSTI]

    Gassend, Blaise L. P. (Blaise Laurent Patrick), 1978-

    2007-01-01T23:59:59.000Z

    This thesis presents the design, fabrication and testing of a fully-integrated planar electrospray thruster array, which could lead to more efficient and precise thrusters for space propulsion applications. The same ...

  19. Propulsion Materials R&D | Clean Energy | ORNL

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

    higher temperature capabilities, emissions reduction, thermal management, and corrosion mitigation. The program utilizes ORNL's unique suite of materials processing,...

  20. Thermal-hydraulics Analysis of a Radioisotope-powered Mars Hopper Propulsion System

    SciTech Connect (OSTI)

    Robert C. O'Brien; Andrew C. Klein; William T. Taitano; Justice Gibson; Brian Myers; Steven D. Howe

    2011-02-01T23:59:59.000Z

    Thermal-hydraulics analyses results produced using a combined suite of computational design and analysis codes are presented for the preliminary design of a concept Radioisotope Thermal Rocket (RTR) propulsion system. Modeling of the transient heating and steady state temperatures of the system is presented. Simulation results for propellant blow down during impulsive operation are also presented. The results from this study validate the feasibility of a practical thermally capacitive RTR propulsion system.