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Thu Oct 16 17:53:05 2014 UTClccn-n20010134350.00Strategic plan : draft /0.791.00Remote-Handled Low Level Waste Disposal Project Alternatives Analysis150284530n 20010134355549131United States. Department of Energy. Office of Nuclear Energy, Science, and TechnologycontainsVIAFID/131327464United States. Department of Energylccn-n84003987United StatesDepartment of EnergyOffice of Scientific and Technical Informationdstlccn-no2006024236Idaho National Laboratoryresspnlccn-n79048535Idaho National Engineering Laboratoryreslccn-n81018718Oak Ridge National Laboratoryresspnlccn-no90021011Fast Flux Test Facility (Wash.)nc-argonne national labArgonne National Labreslccn-no2005020971International Nuclear Energy Research Initiative (U.S.)lccn-no2005093466Nuclear Energy Research Initiative (U.S.)lccn-n78018245United StatesDepartment of EnergyTechnical Information Centerreslccn-no98037589Idaho National Engineering and Environmental LaboratoryresUnited StatesOffice of Nuclear Energy, Science, and TechnologyPeriodicalsUnited StatesNuclear energy--ResearchFast Flux Test Facility (Wash.)Radioisotopes--Environmental aspectsInternational Nuclear Energy Research Initiative (U.S.)Nuclear Energy Research Initiative (U.S.)Nuclear engineering--Study and teaching (Higher)Nuclear energy--Study and teaching (Higher)Nuclear reactorsNuclear energy--Government policyNuclear energyRadioactive waste disposal in the ground--Environmental aspectsSpent reactor fuels--Environmental aspectsLos Alamos National LaboratoryOak Ridge National LaboratoryIdaho National Engineering LaboratoryUnited States.--Office of Nuclear Energy, Science, and TechnologyNuclear energy--International cooperationEnvironmental impact statementsNew MexicoUnited States.--Department of Energy.--Assistant Secretary for Environment, Safety, and HealthEnvironmental policyUnited States.--Department of Energy.--Office of Environmental ManagementExpenditures, PublicNuclear facilities--PlanningNuclear industry--Government policy194419451949195119521953195419551956195719581959196119631964197619791980198119821983198419851986198719881989199019911994199519961997199819992000200120022003200420052006200720082009201020112012430417611799621.4830973E1.20:0310ocn068487014ocn316325740ocn316323186ocn316325697ocn316456751ocn316505298ocn316322758ocn316308833ocn316303628ocn316322605ocn316448766ocn316448775ocn316322800ocn316448731ocn316450304ocn316448780ocn068497485ocn727331110ocn873863746ocn8736166321932ocn058837952com20000.82United StatesFinal programmatic environmental impact statement for accomplishing expanded civilian nuclear energy research and development and isotope production missions in the United States, including the role of the Fast Flux Test Facility1822ocn152595436file0.79International Nuclear Energy Research Initiative (U.S.)Annual reportPeriodicals1802ocn152582317file0.79Nuclear Energy Research Initiative (U.S.)Annual reportPeriodicals1211ocn055484261file0.79University currentsPeriodicals1141ocn001704893serial0.70Nuclear reactors built, being built, or planned in the United States as ofPeriodicals121ocn061187355book20050.33United StatesDraft environmental impact statement for the proposed consolidation of nuclear operations related to production of radioisotope power systems111ocn044741529book20000.59Draft programmatic environmental impact statement for accomplishing expanded civilian nuclear energy research and development and isotope production missions in the United States, including the role of the Fast Flux Test Facility : summary103ocn727181019file20091.00Remote-Handled Low Level Waste Disposal Project Alternatives AnalysisThis report identifies, evaluates, and compares alternatives for meeting the U.S. Department of Energy's mission need for management of remote-handled low-level waste generated by the Idaho National Laboratory and its tenants. Each alternative identified in the Mission Need Statement for the Remote-Handled Low-Level Waste Treatment Project is described and evaluated for capability to fulfill the mission need. Alternatives that could meet the mission need are further evaluated and compared using criteria of cost, risk, complexity, stakeholder values, and regulatory compliance. The alternative for disposal of remote-handled low-level waste that has the highest confidence of meeting the mission need and represents best value to the government is to build a new disposal facility at the Idaho National Laboratory Site81ocn044740770book20000.92Final environmental impact statement for the treatment and management of sodium-bonded spent nuclear fuel : summary82ocn727180980com20101.00Remote-Handled Low-Level Waste Disposal Project Code of RecordThe Remote-Handled Low-Level Waste (LLW) Disposal Project addresses an anticipated shortfall in remote-handled LLW disposal capability following cessation of operations at the existing facility, which will continue until it is full or until it must be closed in preparation for final remediation of the Subsurface Disposal Area (approximately at the end of Fiscal Year 2017). Development of a new onsite disposal facility, the highest ranked alternative, will provide necessary remote-handled LLW disposal capability and will ensure continuity of operations that generate remote-handled LLW. This report documents the Code of Record for design of a new LLW disposal capability. The report is owned by the Design Authority, who can authorize revisions and exceptions. This report will be retained for the lifetime of the facility72ocn727181031com20101.00Conceptual Design Report for Remote-Handled Low-Level Waste Disposal FacilityThis conceptual design report addresses development of replacement remote-handled low-level waste disposal capability for the Idaho National Laboratory. Current disposal capability at the Radioactive Waste Management Complex is planned until the facility is full or until it must be closed in preparation for final remediation (approximately at the end of Fiscal Year 2017). This conceptual design report includes key project assumptions; design options considered in development of the proposed onsite disposal facility (the highest ranked alternative for providing continued uninterrupted remote-handled low level waste disposal capability); process and facility descriptions; safety and environmental requirements that would apply to the proposed facility; and the proposed cost and schedule for funding, design, construction, and operation of the proposed onsite disposal facility71ocn034877769book19960.97United StatesMedical isotopes production project : molybdenum-99 and related isotopes : environmental impact statement72ocn316303628file20051.00Annual Technical Progress Report of Radioisotope Power System Materials Production and Technology Tasks for October 1, 2004 through September 30, 2005The Office of Space and Defense Power Systems of the Department of Energy (DOE) provides Radioisotope Power Systems (RPS) for applications where conventional power systems are not feasible. For example, radioisotope thermoelectric generators were supplied by the DOE to the National Aeronautics and Space Administration for deep space missions including the Cassini Mission launched in October of 1997 to study the planet Saturn. For the Cassini Mission, ORNL produced carbon-bonded carbon fiber (CBCF) insulator sets, iridium alloy blanks and foil, and clad vent sets (CVS) used in the generators. The Oak Ridge National Laboratory (ORNL) has been involved in developing materials and technology and producing components for the DOE for more than three decades. This report reflects program guidance from the Office of Space and Defense Power Systems for fiscal year (FY) 2005. Production activities for prime quality (prime) CBCF insulator sets, iridium alloy blanks and foil, and CVS are summarized in this report. Technology activities are also reported that were conducted to improve the manufacturing processes, characterize materials, or to develop information for new radioisotope power systems62ocn871371384file20071.00Next Generation Nuclear Plant Methods Technical Program PlanOne 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 VHTR61ocn044741506book20000.47Draft programmatic environmental impact statement for accomplishing expanded civilian nuclear energy research and development and isotope production missions in the United States, including the role of the Fast Flux Test Facility61ocn044740776book20000.74Final environmental impact statement for the treatment and management of sodium-bonded spent nuclear fuel62ocn873870183file20101.00Idaho National Laboratory (INL) Site Greenhouse Gas (GHG) Monitoring Plan - 40 CFR 98The purpose of this Greenhouse Gas (GHG) Monitoring Plan is to meet the monitoring plan requirements of Title 40 of the Code of Federal Regulations Part 98.3(g)(5). This GHG Monitoring Plan identifies procedures and methodologies used at the Idaho National Laboratory Site (INL Site) to collect data used for GHG emissions calculations and reporting requirements from stationary combustion and other regulated sources in accordance with 40 CFR 98, Subparts A and other applicable subparts. INL Site Contractors determined subpart applicability through the use of a checklist (Appendix A). Each facility/contractor reviews operations to determine which subparts are applicable and the results are compiled to determine which subparts are applicable to the INL Site. This plan is applicable to the 40 CFR 98-regulated activities managed by the INL Site contractors: Idaho National Laboratory (INL), Idaho Cleanup Project (ICP), Advanced Mixed Waste Treatment Project (AMWTP), and Naval Reactors Facilities (NRF)61ocn068487014com20020.96Interfacial Transport Phenomena and Stability in Molten Metal - Water SystemsINTERFACIAL TRANSPORT PHENOMENA STABILITY in LIQUID-METAL/WATER SYSTEMS M. Corradini, M. Anderson, R. Bonazza Wisconsin Institute of Nuclear Systems University of Wisconsin, Madison 53711Corradini@engr.wisc.edu, http://wins.engr.wisc.edu/D.H. Cho, R. Page Reactor Engineering Division Argonne National Laboratory, Argonne IL 60439cho@daisy.re.anl.govOne concept being considered for steam generation in innovative nuclear reactor applications, involves water coming into direct contact with a circulating molten metal. The vigorous agitation of the two fluids, the direct liquid-liquid contact and the consequent large interfacial area can give rise to large heat transfer coefficients and rapid steam generation. For an optimum design of such direct contact heat exchange and vaporization systems, detailed knowledge is necessary of the various flow regimes, interfacial transport phenomena, heat transfer and operational stability.In order to investigate the characteristics of such a molten metal/water direct contact heat exchanger, a series of experiments were performed in both a 1-D and 2-d experimental facility. The facilities primarily consist of a liquid-metal melt chamber, heated test section, water pumping/injection system, and steam suppression tank (condenser). A real-time high energy X-ray imaging system along with several temperature measurements and flow measurements were developed and utilized to measure the multiphase flow and obtain an empirical database of local as well as overall system parameters. Results have found volumetric void fraction between 0.05-0.2, overall volumetric heat transfer coefficient ranging from 4-20 kW/m3K, evaporation zone lengths on the order of 10cm and local heat transfer coefficients varying between 500-5000 W/m2K depending on the inlet water injection conditions and system pressure. Time-dependent void fraction distribution and generated water-vapor bubble characteristics (i.e. bubble formation rate, bubble rise velocity, and bubble surface area) were measured using an X-ray image analysis technique. These measurements aided in the determination of the volumetric thermal performance as well as well as the first detailed information on local interfacial phenomenon. This information in turn resulted in the first experimental measurements of the local heat transfer coefficient at different locations within the liquid metal pool. The effect of the system operating pressure and the water injection rate on the performance and the stability of the liquid metal/water direct contact heat exchange was obtained and are reported in detail within the following report. The effects of water injection from a 2.0 mm nozzle at flow rates from 1.5g/s to 8g/s into a heavy liquid metal (Pb and Pb/Bi alloy) at temperatures of 300-500 oC and system pressures ranging from 1- 10 bar were investigated. These conditions were chosen to span the two major flow regimes (nucleate and film boiling) that may be present in reactor based direct contact systems. Detailed information regarding the thermal performance and the operational stability of a liquid metal/water direct contact heat exchange were obtained for these conditions. The resulting extensive experimental database can be used to aid in the design of reactor scale components dealing with high temperature direct contact heat transfer63ocn727349146com20071.00Next Generation Nuclear Plant System Requirements Manual63ocn727347153com20071.00Advanced Fuel Cycle Cost BasisThis report, commissioned by the U.S. Department of Energy (DOE), provides a comprehensive set of cost data supporting a cost analysis for the relative economic comparison of options for use in the Advanced Fuel Cycle Initiative (AFCI) Program. The report describes the AFCI cost basis development process, reference information on AFCI cost modules, a procedure for estimating fuel cycle costs, economic evaluation guidelines, and a discussion on the integration of cost data into economic computer models. This report contains reference cost data for 25 cost modules--23 fuel cycle cost modules and 2 reactor modules. The cost modules were developed in the areas of natural uranium mining and milling, conversion, enrichment, depleted uranium disposition, fuel fabrication, interim spent fuel storage, reprocessing, waste conditioning, spent nuclear fuel (SNF) packaging, long-term monitored retrievable storage, near surface disposal of low-level waste (LLW), geologic repository and other disposal concepts, and transportation processes for nuclear fuel, LLW, SNF, transuranic, and high-level waste31ocn051755531file0.96United StatesOffice of Nuclear Energy, Science and Technology-DOE32ocn036366173book19960.96United StatesThe Department of Energy's FY 1997 budget requests for environment, safety and health, environmental restoration and waste management (non-defense) and nuclear energy : hearing before the Subcommittee on Energy and Environment of the Committee on Science, U.S. House of Representatives, One Hundred Fourth Congress, second session, May 1, 199631ocn183889154file0.26United StatesOffice of Nuclear Energy, Nuclear Energy-DOE11ocn036197492book1995United StatesStrategic plan : draftThu Oct 16 16:00:55 EDT 2014batch46094