WorldCat Identities

United States Office of Nuclear Energy, Science, and Technology

Overview
Works: 1,403 works in 1,450 publications in 1 language and 2,299 library holdings
Genres: Periodicals  Directories 
Roles: Sponsor, Researcher
Classifications: E1.20:0310, 621.4830973
Publication Timeline
Key
Publications about United States Publications about United States
Publications by United States Publications by United States
Most widely held works by United States
Annual report by International Nuclear Energy Research Initiative (U.S.) ( )
in English and held by 163 WorldCat member libraries worldwide
Annual report by Nuclear Energy Research Initiative (U.S.) ( )
in English and held by 161 WorldCat member libraries worldwide
Nuclear reactors built, being built, or planned in the United States as of ( )
in English and held by 115 WorldCat member libraries worldwide
University currents ( )
in English and held by 101 WorldCat member libraries worldwide
Final environmental impact statement for the treatment and management of sodium-bonded spent nuclear fuel : summary ( Book )
2 editions published in 2000 in English and held by 13 WorldCat member libraries worldwide
Draft environmental impact statement for the proposed consolidation of nuclear operations related to production of radioisotope power systems by United States ( Book )
1 edition published in 2005 in English and held by 12 WorldCat member libraries worldwide
Medical isotopes production project : molybdenum-99 and related isotopes : environmental impact statement by United States ( Book )
1 edition published in 1996 in English and held by 7 WorldCat member libraries worldwide
Final programmatic environmental impact statement for alternative strrategies for the long-term management and use of depleted uranium hexafluoride : summary, April 1999 by United States ( Book )
1 edition published in 1999 in English and held by 5 WorldCat member libraries worldwide
The Next Generation Nuclear Plant ( )
5 editions published between 2007 and 2009 in English and held by 5 WorldCat member libraries worldwide
The Next Generation Nuclear Plant (NGNP) will be a demonstration of the technical, licensing, operational, and commercial viability of High Temperature Gas-Cooled Reactor (HTGR) technology for the production of process heat, electricity, and hydrogen. This nuclear- based technology can provide high-temperature process heat (up to 950°C) that can be used as a substitute for the burning of fossil fuels for a wide range of commercial applications (see Figure 1). The substitution of the HTGR for burning fossil fuels conserves these hydrocarbon resources for other uses, reduces uncertainty in the cost and supply of natural gas and oil, and eliminates the emissions of greenhouse gases attendant with the burning of these fuels. The HTGR is a passively safe nuclear reactor concept with an easily understood safety basis that permits substantially reduced emergency planning requirements and improved siting flexibility compared to other nuclear technologies
Power Burst Facility ( )
4 editions published in 1990 in English and held by 4 WorldCat member libraries worldwide
This report discusses the monthly progress of the Power Burst Facility/Boron Neutron Capture Therapy (PBF/BNLT) program for cancer treatment. Highlights of the PBF/BNCT Program during July 1990 include progress within the areas of: Gross boron analysis in tissue, blood, and urine; noninvasive boron quantitative determination; analytical radiation transport and interaction modeling for BNCT; large animal model studies; neutron source and facility preparation; administration and common support and PBF operations
100-F unit purge ( )
4 editions published in 1945 in English and held by 4 WorldCat member libraries worldwide
Medical isotopes production project : molybdenum-99 and related isotopes : draft environmental impact statement by United States ( Book )
1 edition published in 1995 in English and held by 4 WorldCat member libraries worldwide
Improving the safety of Soviet-designed nuclear power plants : status report ( Book )
1 edition published in 1996 in English and held by 4 WorldCat member libraries worldwide
DEVELOPMENT OF A NOVEL SOLVENT FOR THE SIMULTANEOUS SEPARATION OF STRONTIUM AND CESIUM FROM DISSOLVED SPENT NUCLEAR FUEL SOLUTIONS ( )
2 editions published in 2004 in English and held by 3 WorldCat member libraries worldwide
The recovery of Cs and Sr from acidic solutions by solvent extraction has been investigated. The goal of this project was to develop an extraction process to remove Cs and Sr from high-level waste in an effort to reduce the heat loading in storage. Solvents for the extraction of Cs and Sr separately have been used on both caustic and acidic spent nuclear fuel waste in the past. The objective of this research was to find a suitable solvent for the extraction of both Cs and Sr simultaneously from acidic nitrate media
Interfacial Transport Phenomena and Stability in Molten Metal - Water Systems ( )
1 edition published in 2002 in English and held by 3 WorldCat member libraries worldwide
INTERFACIAL 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 transfer
Advanced Fuel Cycle Cost Basis ( )
3 editions published between 2007 and 2009 in English and held by 3 WorldCat member libraries worldwide
This 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 waste
Draft progammatic environmental impact statement for alternative strategies for the long-term management and use of depleted uranium hexafluoride ( Book )
2 editions published in 1997 in English and held by 3 WorldCat member libraries worldwide
 
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Alternative Names

controlled identity United States. Department of Energy

United States. Department of Energy. Office of Nuclear Energy, Science, and Technology
Languages
English (45)