Oak Ridge National Laboratory
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The organization Oak Ridge National Laboratory represents an institution, an association, or corporate body that is associated with resources found in Indiana State Library.
The Resource
Oak Ridge National Laboratory
Resource Information
The organization Oak Ridge National Laboratory represents an institution, an association, or corporate body that is associated with resources found in Indiana State Library.
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- Oak Ridge National Laboratory
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- (EG-IN)1182376
100+ Items by the Organization Oak Ridge National Laboratory
9 Items that are about the Organization Oak Ridge National Laboratory
Context
Context of Oak Ridge National LaboratoryContributor of
- 1978 DOE Statistical Symposium, November 1-3, 1978, Sandia Laboratories, Albuquerque, New Mexico
- 1990 NPTS databook
- 1990 NPTS databook : based on data from the 1990 Nationawide Personal Transportation Survey (NPTS), Vol. II
- 52nd Colloid and Surface Science Symposium, June 12-14, 1978 : proceedings volume
- A 1-D transport model for analysis of expanding radius and full bore startup of tokamak plasmas/
- A CHORD simulation for insult assessment to the red bone marrow
- A bibliography on moving boundary problems with key word index
- A characterization of check valve degradation and failure experience in the nuclear power industry
- A comparative evaluation of recent reports on the energy conservation potential from cogeneration
- A comparison of beam deposition for three neutral beam injection codes
- A computerized management report for monitoring spending : a user's manual
- A computerized management report system for monitoring manpower and cost
- A critical review of the practice of equating the reactivity of spent fuel to fresh fuel in burnup credit criticality safety analyses for PWR spent fuel pool storage
- A damage mechanics based approach to structural deterioration and reliability
- A literature survey : methods for the removal of iodine species from off-gases and liquid waste streams of nuclear power and nuclear fuel reprocessing plants, with emphasis on solid sorbents
- A matrix approach to biological investigation of synthetic fuels : proceedings of a conference cosponsored by the U.S. Environmental Protection Agency and Oak Ridge National Laboratory through the EPA/DOE Fossil Fuels Research Materials Facility, Research Triangle Park, North Carolina, April 26, 1979
- A method and case study for estimating the ramping capability of a control area or balancing authority and implications for moderate or high wind penetration : preprint
- A methodology for evaluation of inservice test intervals for pumps and motor-operated valves
- A microcomputer-controlled ultrasonic data acquisition system
- A preliminary economic analysis of aquifer winter-chill storage at the John F. Kennedy Airport
- A probability prediction model of mouse skin tumors based on the chemical components of cigarette smoke condensates
- A procedure for estimating nonfuel operating and maintenance costs for large steam-electric power plants
- A procedure for estimating nonfuel operation and maintenance costs for large steam-electric power plants
- A program to calculate deformation mechanism maps using an HP-9821A calculator
- A ray tracing package through a lens system and spectrometer
- A review of information relevant to tube corrosion in a gas-cooled, coal-fired, atmospheric-pressure, fluidized-bed furnace
- A review of large-scale fracture experiments relevant to pressure vessel integrity under pressurized thermal shock conditions
- A revised version of SLIDES : a program to draw slides and posters
- A risk-informed basis for establishing non-fixed surface contamination limits for spent fuel transportation casks
- A simple measure of merit for fusion feasibility
- A summary of procedures used to transport and distribute consumer products
- A user's guide to program MAD : a computer program for the organization and manipulation of magnetic tape directories
- A user's guide to the CALVEC software library : a computer program for emulation of CALCOMP graphics on a versatec printer/plotter
- A user's manual for the contaminant transport module of the MIGRAT code
- A working hypothesis to explain mortalities of striped bass, morone saxatilis, in Cherokee Reservoir
- ANS Topical Meeting on Radiological Accidents--Perspectives and Emergency Planning, September 15-17, 1986, Holiday Inn, Bethesda, MD : program and abstracts
- Acid in perchloroethylene scrubber solutions used in HTGR fuel preparation processes : analytical chemistry studies
- Actinide recovery from combustible waste : the Ce(IV)-HNO3 system
- Advanced reactor licensing : experience with digital I&C technology in evolutionary plants
- Advnces in reactor physics : proceedings of an American Nuclear Society topical meeting, Gatlinburg, Tennessee, April 10-12, 1978
- Aging and service wear of check valves used in engineered safety-feature systems of nuclear power plants
- Aging and service wear of control rod drive mechanisms for BWR nuclear plants
- Aging and service wear of electric motor-operated valves used in engineering safety-feature systems of nuclear power plants
- Aging assessment of reactor instrumentation and protection system components : aging-related operating experiences
- Aging of control and service air compressors and dryers used in nuclear power plants
- Air quality and point source emissions data for the Southern United States
- Alpha-driven, steady-state tokamak
- Alternate nuclear waste forms and interactions in geologic media : proceedings of a workshop summarizing advanced activities and formulating requirements for the future, May 13-15, 1980, Gatlinburg, Tennessee
- Alternative fuel cycle PWR models for the ORIGEN computer code
- An Evaluation of the Long-Term Energy Analysis Program used for the 1978 EIA administrator's report to Congress
- An analysis of excursions at selected in situ uranium mines in Wyoming and Texas
- An assessment of anomalies in the EEI data base on power plant performance
- An assessment of materials for use in a solar ceramic receiver for chemical process heat
- An economic data base for alternative nuclear fuel cycle evaluations for U.S. electrical utility industry conditions
- An economic engineering energy demand model for the pulp and paper industry
- An economic feasibility assessment of the Oak Ridge National Laboratory waste-heat polyculture concept
- An economic impact analysis of energy facilities with particular reference to the Hartsville, Tennessee, area
- An evaluation of the effectiveness of selected corrosion inhibitors for protection of prestressing steels in PCPVs
- An investigation of crack-tip stress field criteria for predicting cleavage-crack initiation
- An investigation of plutonium concentration and distribution in burrowing crayfish from the White Oak Creek floodplain
- An investigation of tendon sheathing filler migration into concrete
- An optimization of the fission-fusion hybrid concept
- An overview of the low-upper-shelf toughness safety margin issue
- An updated nuclear criticality slide rule
- Analysis and computer programs for eddy current coils concentric with multiple cylindrical conductors
- Analysis of H.B. Robinson PWR vessel fluence for cycle 10 utilizing partial length shield assemblies
- Analysis of UO3
- Analysis of ZPPR-5 source level flux monitor experiments
- Analysis of a cordierite (MAS) recuperator from a molybdenum heat -treating furnace
- Analysis of a nuclear backscattering and reaction data by the method of convolution integrals
- Analysis of blind flange and thermowell assembly from Wilsonville, Alabama, solvent refined coal plant dissolver tank
- Analysis of fission-product effects in a fast mixed-spectrum reactor concept
- Analysis of level control valve seat from the recycle condensate separator at the Ft. Lewis Washington, SRC pilot plant
- Analysis of particle species evolution in neutral beam injection lines
- Analysis of potential implementation levels for waste heat utilization in the nuclear power industry
- Analysis of the VENUS-3 experiments
- Analysis of the chemical composition of streamflow components
- Analysis of the continuous cycling fatigue behavior of 2 1/4 Cr-1 Mo steel
- Analysis of the impurity flow reversal experiment
- Analysis of vehicle classification and truck weight data of the New England States : final report
- Analytic model for the nonlinear interaction of tearing modes of different pitch in cylindrical geometry
- Analytic, high β, flux conserving equilibria for cylindrical tokamaks
- Analytical investigation of multicavity prestressed concrete pressure vessels for elastic loading conditions : HTGR base technology program : prestressed concrete nuclear pressure vessel development (189a 01331), Milestone no. 1c
- Analytical studies of transverse strain effects on fracture toughness for circumferentially oriented cracks
- Anomalous alpha particle transport in thermonuclear tokamak plasma
- Applicabilty of high-n ballooning theory
- Application of microprocessor-based equipment in nuclear power plants : technical basis for a qualification methodology : draft report for comment
- Application of the NCSA Habanero tool for collaboration on structural integrity assessments
- Applications of energy release rate techniques to part-through cracks in plates and cylinders
- Assessment and recommendations for fissile-material packaging exemptions and general licenses within 10 CFR Part 71
- Assessment of Donnlee 3000-horsepower TurboFireXL boiler
- Assessment of radiological releases to the environment from a fusion reactor power plant
- Assessment of wireless technologies and their application at nuclear facilities
- Association of radionuclides with streambed sediments in White Oak Creek watershed
- Atom probe tomography characterization of the solute distributions in a neutron-irradiated and annealed pressure vessel steel weld
- Auxiliary feedwater system aging study
- Auxiliary feedwater system aging study
- BGSUB and BGFIX, FORTRAN programs to correct Ge(Li) gamma-ray spectra for photopeaks from radionuclides in background
- BWR Mark II ex-vessel corium interaction analyses
- Background information and technical basis for assessment of environmental implications of magnetic fusion energy
- Beam profiles from multiple aperture sources
- Beam steering due to displaced slots
- Biaxial loading and shallow-flaw effects on crack-tip constraint and fracture toughness
- Biomass energy : focus on wood waste
- Blast tests of expedient shelters in the dice throw event
- Boiling-water reactor internals aging degradation study : phase 1
- Budden tunneling in parallel stratified plasmas
- Bulk shielding facility quarterly report
- Burnout conditions in BSR cores under forced convection flow
- CARP, a computer code and albedo data library for use by BREESE, the MORSE albedo package
- CONTUR, a subroutine to draw contour lines for randomly located data
- COVERT and CAVALIER, two computer codes for estimating uncertainties of calculated neutronics parameters using standard interface files SENPRO and COVERX
- CSNI Project for Fracture Analyses of Large-Scale International Reference Experiments (Project FALSIRE)
- Calculated, two-dimensional dose rates from a PWR fuel assembly
- Calculation of absorbed doses to water pools in severe accident sequences
- Calculations pertaining to the design of a prebuncher for a 150-MeV electron linear accelerator
- Calorimetric assay of HTGR fuel samples
- Carcinogenic risk of lead-210 and polonium-210 in tobacco smoke : a selected, annotated bibliography
- Central cooling -- compressive chillers
- Characterization of operating conditions for gas/water heat recovery steam generators
- Characterization of pyrocarbon coatings of HTGR fuel particles by inert gas intrusion
- Characterization of selected application of biomass energy technologies and a solar district heating & cooling system
- Cladding of pressure vessel steels for coal conversion applications : a literature review
- Coal dissolution studies : particle size distribution in coal-derived liquids as a function of degree of coal conversion
- Coexistence assessment of industrial wireless protocols in the nuclear facility environment
- Comparison of U.S. military and international electromagnetic compatibility guidance : final report
- Comparison of irradiation-induced shifts of Kjc and charpy impact toughness for reactor pressure vessel steels
- Compatibility of Pt-3008 with selected components of the selenide isotope generator system
- Computational benchmark for estimation of reactivity margin from fission products and minor actinides in PWR burnup credit
- Computer automation of an electron-beam welder with autormatic, stored seam tracking
- Computer programs for eddy-current defect studies
- Computer programs for the acquisition and analysis of eddy-current array probe data
- Concept evaluation of a nuclear design for electronuclear fuel production : evaluation of ORNL's proposed TMF-ENFP
- Conceptual design of the LCP coil support structure
- Concrete component aging and its significance relative to life extension of nuclear power plants
- Condensation on refrigerants on vertical fluted tubes
- Constraint effects on fracture toughness for circumferentially oriented cracks in reactor pressure vessels
- Construction data and retrieval procedures for selected wells drilled from 1985 through 1987 at Oak Ridge National Laboratory, Tennessee
- Control of hydrocarbon and carbon monoxide emissions in the tail gases from coal gasification facilities
- Conventional alternating-current generators and engine generator sets
- Conversion between cold plasma modes in an inhomogeneous plasma
- Correlation of physical coal separation
- Corrosion manual for internal corrosion of water distribution systems
- Corrosion of alloy 800H in caustic-contaminated superheated steam at 538C̊ (1000F̊)
- Corrosivity of geothermal brines : progress report for period ending September 1977, final report
- Crack-arrest behavior in SEN wide plates of low-upper-shelf base metal tested under nonisothermal conditions : WP-2 series
- Crack-arrest tests on two irradiated high-copper welds : phase II : results of duplex-type experiments
- Creep behavior of Hastelloy X, 2 1/4 Cr-1 Mo steel, and other alloys in simulated HTGR helium
- Criticality analysis of aggregations of actinides from commercial nuclear waste in geological storage
- Criticality analysis of assembly misload in a PWR burnup credit cask
- Cross sections for the Cu(n,xn) and Cu (n,xγ) reactions between 1 and 20 MeV
- Cross sections for the Ti(n,xn) and Ti(n,xγ) reactions between 1 and 20 MeV
- Current applications of vibration monitoring and neutron noise analysis
- Current applications of vibration monitoring and neutron noise analysis : detection and analysis strutural degradation of reactor vessel internals from operational aging
- D-D neutron measurements on a 40-kV, 60-A neutral beam test facility
- DOGS--a collection of graphics for support of discrete ordinates codes
- Data analysis for steam generator tubing samples
- Data summary report for fission product release test VI-1
- Data summary report for fission product release test VI-2
- Data summary report for fission product release test VI-3
- Data summary report for fission product release test VI-4
- Data summary report for fission product release test VI-5
- Data summary report for fission product release test VI-6
- Density, acidity and conductivity measurements of uranyl nitrate/nitric acid solutions
- Density-wave instabilities in boiling water reactors
- Deposition of silicon carbide coatings on particles in a fluidized bed using silane and tetramethylsilane : a feasibility study
- Desalting seawater and brackish water : cost update, 1979
- Design and performance testing of a coal feed and metering system for the MIUS fluidized-bed combustor
- Design calculations for a 14-MeV neutron collimator
- Design of viewing windows for controlled-atmosphere chambers
- Detection and characterization of indications in segments of reactor pressure vessels
- Detection of gas-permeable fuel particles for high-temperature gas-cooled reactors
- Detection of hydrogen buildup in initially pure nonhydrogenous liquids
- Determination of end-of-life-failure fractions of HTGR-fuel particles by postirradiation annealing and beta autoradiography
- Determination of the neutron and gamma flux distribution in the pressure vessel and cavity of a boiling water reactor
- Development and validation of light-duty modal emissions and fuel consumption values for traffic models
- Development of a high efficiency automatic defrosting refrigerator/freezer : phase I--design and development
- Development of cementitious grouts for the incorporation of radioactive wastes: : part 2, continuation of cesium and strontium leach studies
- Development of depletion perturbation theory for coupled neutron/nuclide fields
- Development of relationship between truck accidents and geometric design, Phase I
- Development program for a 200 kW, CW, 28-GHz gyroklystron
- Diffusion form solid cylinders
- Diffusion into a hollow cylinder
- District Heating/Cogeneration Symposium
- District heating/cogeneration application studies for the Minneapolis-St. Paul area : executive summary, overall feasibility and economic viability for a district heating/new cogeneration system in Minneapolis-St. Paul
- Documentation of the resource allocation and mine costing (RAMC) model
- Draft program plan for TNS, the next step after the tokamak fusion test reactor
- Dynamic fracture initiation toughness of ASTM A533, Grade B steel plate
- Dynamic fracture initiation toughness of ASTM A533, Grade B steel plate
- EDISTR--a computer program to obtain a nuclear decay data base for radiation dosimetry
- ELMO Bumpy Torus
- Eastern decidous forest biome progress report
- Economics of the ANFLOW process for municipal sewage treatment
- Eddy current heating of irregularly shaped plates by slow ramped fields
- Effect of oxidizing environment on mechanical properties of molybdenum and TZM
- Effect of particle blending on HTGR fuel rod temperature profiles : HTGR fuel recycle development program (189a OHO45) Fuel Refabrication, task 500
- Effect of welding conditions on transformation and properties of heat-affected zones in LWR vessel steels
- Effects of aging and service wear on main steam isolation valves and valve operators
- Effects of alternate fuels
- Effects of hot electrons on magnetohydrodynamic modes in EBT
- Effects of intermediate ethanol blends on legacy vehicles and small non-road engines, report 1 -- updated
- Effects of mineralogy on sorption of strontium and cesium onto Calico Hills tuff
- Effects of nonstandard heat treatment temperatures on tensile and charpy impact properties of carbon-steel casting repair welds
- Elastic energy and metastable phase equilibria for coherent mixtures in cubic systems
- Electricity in lieu of natural gas and oil for industial thermal energy : a preliminary survey
- Electromagnetic compatibility testing for conducted susceptibility along interconnecting signal lines : final report
- Electron cyclotron heating rate and cavity Q estimations for an EBT plasma
- Electron-beam welding of thorium-doped iridium alloy sheets
- Electron-cyclotron heating of toroidal plasma with emphasis on results from the ELMO Bumpy Torus (EBT)
- Embrittlement data base, version 1
- Energy and cost analysis of residential heating systems
- Energy conservation opportunities in commercial appliances
- Energy demand and fuel choices in the pulp and paper industry
- Energy economic data base (EEDB) program : phase VIII update (1986), BWR supplement
- Engineering-economic analysis of mobile home thermal performance
- Engineering-economic analysis of single-family dwelling thermal performance
- Environmental assessment : San Bernardino National Wildlife Refuge well 10
- Environmental assessment : renewal of materials licenses for ALARON Corp. Northeast Regional Service Facility, Wampum, Pennsylvania
- Environmental testing of an experimental digital safety channel
- Estimatation of costs for fabrication of pressurized-water reactor fuel
- Estimating the cost of product water conveyance from desalination plants
- Evaluation and field validation of eddy-current array probes for steam generator tube inspection
- Evaluation of 232TH(n,n'), (n,2n) and (n,3n) cross sections
- Evaluation of MHTGR fuel reliability
- Evaluation of WF-70 weld metal from the Midland Unit 1 reactor vessel
- Evaluation of crack pop-ins and the determination of their relevance to design considerations
- Evaluation of creep and relaxation data for Hastelloy alloy X sheet
- Evaluation of terminated licenses parts 30, 40, and 70 : the terminated license tracking system
- Evaluation of terminated nuclear material licenses : a report of identified sites and sealed source licenses
- Evaluation of the French Haut Taux de Combustion (HTC) critical experiment data
- Evolution of flux conserving tokamak equilibria with preprogrammed cross sections
- Experimental and analytical investigation of the shallow-flaw effect in reactor pressure vessels
- Experimental results of tests to investigate flaw behavior of mechanically loaded stainless steel clad plates
- Experimental testing and analytical analysis of a plastic panel heat exchanger for greenhouse heating
- Experiments with a lime slurry in a stirred tank for the fixation of carbon-14-contaminated CO2 from simulated HTGR fuel reprocessing off-gas
- Exposure calculation code module for reactor core analysis : BURNER
- External exposure to radionuclides in air, water, and soil : exposure-to-dose coefficients for general application, based on the 1987 federal radiation protection guidance
- Extrapolation of the J-R curve for predicting reactor vessel integrity
- FFCG, a free-form input combinatorial geometry package
- FLOCHT, a system of Fortran codes for computer drawn flow charts and diagrams
- FORM, perspective plotting code for one- and two-dimensional fluxes
- Feasibility of citizen construction of expedient fallout shelters : final report
- Feasibility of conducting wetfall chemistry investigations around the Bowen Power Plant
- Feasibility of high frequency acoustic imaging for inspection of containments
- Feasibility of magnetostrictive sensor inspection of containments
- Fibrous alumina-silica insulation board as a candidate Standard Reference Material of thermal resistance
- Fifteenth nuclear accident dosimetry intercomparison study, August 14-22, 1978
- Fifth personnel dosimetry intercomparison study
- Final report, assessment of potential phosphate ion-cementitious materials interactions
- Fission product Pd-SiC interaction in irradiated coated fuel particles
- Fission product behavior in HTGR fuel particles made from weak-acid resins
- Fission product plateout and liftoff in the MHTGR primary system : a review
- Fort Saint Vrain gas cooled reactor operational experience
- Fortran subroutines for bicubic spline interpolation
- Fossil energy program
- Fourth personnel dosimetry intercomparison study
- Fracture analysis of vessels : Oak Ridge FAVOR, v.04.1, computer code : users guide
- Fracture-mechanics-based failure analysis
- Fragility modeling of aging containment metallic pressure boundaries
- Friction and wear characteristics of molecular compound classes from lubricating base oils
- Fuel choice and aggregate energy demand in the commercial sector
- Fuel consumption and emission values for traffic models
- Functional issues and environmental qualification of digital protection systems of advanced light-water nuclear reactors
- GCFR 1/15-scale PCRV steam generator cavity closure half-thickness model test
- GCFR radial blanket and shield experiment : objectives, preanalysis, and specifications
- GHPs improve housing and save energy at Camp Lejeune
- GOFRR : a computer code to generate graphical output of DOT and ANISN fluxes and reaction rates
- Gas centrifuge enrichment plant seismic time history development
- Gas space heating equipment modifications
- Gas turbines
- Gas-cooled reactor programs
- Gaseous dielectrics : proceedings of the International Symposium on Gaseous Dielectrics, Knoxville, Tennessee, USA, March 6-8, 1978
- Gaseous fission product release during storage at various temperatures for HTGR-type fuels : HTGR fuel recycle development program (189a OH 045) reprocessing development (Task 310)
- Generic analyses for evaluation of low Charpy upper-shelf energy effects on safety margins against fracture of reactor pressure vessels
- Generic assessment of radiation exposures to workers in a portable smelter and to the surrounding population
- Geological and geochemical aspects of uranium deposits
- Geometric view factors for axial radiative heat exchange within a straight hollow tube : advanced fuel recycle program
- Gradient study of a large weld joining two forged A 508 shells of the Midland reactor vessel
- Guide to verification and validation of the SCALE-4 criticality safety software
- Guide to verification and validation of the SCALE-4 radiation shielding software
- Guidelines for estimating nonfuel operation and maintenance costs for alternative nuclear power plants
- H.B. Robinson-2 pressure vessel benchmark
- HTAS2, a three-dimensional transient shipping cask analysis tool
- HTGR fuel rod deconsolidation
- Handbook of selected organ doses for projections common in pediatric radiology
- Health physics instrument manual
- Health physics positions data base
- Health physics positions data base
- Heat exchanger design for desalination plants : review of the Office of Saline Water Research and Development Program
- Heat transfer performance of an air-cooled tube in a fluidized-bed furnace
- Heat transfer studies in salt and granite
- Heavy-section steel irradiation program
- Heavy-section steel irradiation program
- Heavy-section steel technology program
- High n ballooning modes in highly elongated tokamaks
- High pressure pumps, drivers, and energy recovery devises for large seawater reverse osmosis plants
- High-level waste program progress report for April 1, 1979 through June 30, 1979
- High-level waste program progress report for October 1, 1978, through March 31, 1979
- High-temperature crack-arrest behavior in 152-mm-thick SEN wide plates of quenched and tempered A 533 grade B class 1 steel
- High-temperature crack-arrest tests using 152-mm-thick SEN wide plates of low-upper-shelf base material : tests WP-2.2 and WP-2.6
- High-temperature gas-cooled reactor base-technology program
- High-temperature gas-cooled reactor fuel recycle development
- High-temperature gas-cooled reactor safety studies for the Division of Accident Evaluation quarterly progress report
- High-temperature oxidation of graphite rods with temperature control by combustion gas recycle
- Human factors issues associated with advanced instrumentation and controls technologies in nuclear plants
- Human genome news
- Hydraulic fracturing as a method for the disposal of volatile radioactive wastes
- Hydrodynamics of three-phase fluidized beds
- Ichiban : radiation dosimetry for the survivors of the bombings of Hiroshima and Nagasaki
- Immunoassay kit : EnviroLogix, Inc. PCB in Soil Tube Assay
- Impact of ENDF/B-VI cross-section data on H.B. Robinson cycle 9 dosimetry calculations
- Impact of structural aging on seismic risk assessment of reinforced concrete structures in nuclear power plants
- Impact of the heat transfer coefficient on pressurized thermal shock
- Improved eddy-current inspection for steam generator tubing progress report for period January 1985 to December 1987
- In situ physical/chemical treatment technologies for remediation of contaminated sites : applicability, development status, and research needs
- In-line tritium monitoring in the GCFR vented irradition capsule GB-10
- In-pile steam oxidation of model HTGR fuel elements
- Inclusion of unstable ductile tearing and extrapolated crack-arrest toughness data in PWR vessel integrity assessment
- Indexgen, index term generation heuristics : software documentation
- Influence of long-term thermal aging on the microstructural evolution of nuclear reactor pressure vessel materials : an atom probe study
- Initial results of the influence of biaxial loading on fracture toughness
- Initial simulation and control system studies of the MIUS coal-fired turbine experiment
- Injection-dominated tokamak experiments at ORNL
- Instabilities in a coal-burning fluidized bed
- Instrumentation and controls in nuclear power plants : an emerging technologies update
- Instrumentation requirements for radiological defense of the U.S. population in community shelters : final report
- Interactive programs for low-flow frequency analyses for use in regional studies
- Interlaboratory comparison of the guarded horizontal pipe-test apparatus : precision of ASTM standard test method C-335 applied to mineral-fiber pipe insulation
- Intermediate report on the performance of plate-type ice-maker heat pumps
- International comparative assessment study of pressurized thermal shock in reactor pressure vessels
- Interpreting forest and grassland biome productivity utilizing nested scales of image resolution and biogeographical analysis
- Invasive plants and their effects on public and provate lands
- Iodine chemical forms in LWR severe accidents : draft report for comment
- Iodine chemical forms in LWR severe accidents : final report
- Iodine evolution and pH control
- Iodine speciation and partitioning in PWR steam generator accidents : final report
- Iodine volatility and pH control in the AP-600 reactor
- Irradiation effects on charpy impact and tensile properties of low upper-shelf welds, HSSI series 2 and 3
- Irradiation effects on fracture toughness of two high-copper submerged-arc welds, HSSI series 5
- Irradiation effects on strength and toughness of three-wire series-arc stainless steel weld overlay cladding
- Irradiaton creep by climb-enabled glide of dislocations resulting from preferred absorption of point defects
- Is there life after TDHF? : a report based on a talk presented at the 1978 Gordon Conference on Nuclear Chemistry, June 19-23
- KENO3D visualization tool for KENO V.a and KENO-VI geometry models
- Kinetics of silica deposition from simulated geothermal brines
- LAPUR benchmark against in-phase and out-of-phase stability tests
- LAPUR user's guide
- LAPUR5.2 verification and user's manual
- LSFODF, a generalized nonlinear least-squares fitting program for use with ORELA ODF files
- Lab notes
- Langmuir probe measurements of the scrape-off plasma in ISX-A
- Lecture notes on ordinary differential equations software : user's guides for ODE, RKF45, GEAR, and EPISODE
- Limited burnup credit in criticality safety analysis : a comparison of ISG-8 and current international practice
- Low BTU coal gasification processes
- Low temperature thermal-energy storage
- Low z impurity transport in tokamaks
- Lower-bound initiation toughness with a modified-Charpy specimen
- MORECA, a computer code for simulating modular high-temperature gas-cooled nuclear reactor core heatup accidents
- MORECA-2 : interactive simulator for modular high-temperature gas-cooled reactor core transients and heatup accidents with ATWS options
- Magnitude and reactivity consequences of moisture ingress into the modular high-temperature gas-cooled reactor core
- Major plasma disruptions in TNS
- Marble Hill annealing demonstration evaluation
- Mass and emission spectrometry in the Analytical Chemistry Division of Oak Ridge National Laboratory
- Mass transfer in two-phase nondispersing liquid-liquid contactors with a high-density-difference system
- Materials & components in fossil energy applications : a newsletter of the U.S. Department of Energy, Advanced Research and Technology Development Materials Program, and the Electronic Power Research Institute
- Materials and design bases issues in ASME code case N-47
- Materials preparation and characterization capabilities : November 16-18, 1982, Oak Ridge, Tennessee
- Mathematical description of adsorption and transport of reactive solutes in soil : a review of selected literature
- Mathematical structure of the international coal trade model
- Measurement error in pressure-decay leak testing / J. N. Robinson
- Measurement of 238U(n,nγ́) and 7Li (n,nγ́) gamma-ray production cross sections
- Measurements and analysis of the CRBR inconel-stainless steel radial shield experiment
- Measuring and interpreting VOCs in soils : state of the art and research needs : a symposium summary, Las Vegas, NV, January 12-14, 1993
- Metallurgical and mechanical properties of thorium-doped Ir-0.3% W alloys
- Method for estimating the lattice thermal conductivity of metallic alloys
- Methodologies for evaluating long-term stabilization designs of uranium mill tailings impoundments
- Methodology for reliability based condition assessment : application to concrete structures in nuclear plants
- Microporous fumed-silica insulation board as a candidate Standard Reference Material of thermal resistance
- Microstructural characterization of selected AEA/UCSB model FeCuMn alloys
- Microwave coupling in EBT reactor
- Mission survey for the Pressure Vessel Research User's Facility (PVRUF)
- Model of a fission counter system for optimizing performance at high gamma dose rates
- Modeling and performance of the MHTGR reactor cavity cooling system
- Models for impurity effects in tokamaks
- More efficient creep ratcheting bounds
- Multiple system responses program : identification of concerns related to a number of specific regulatory issues
- Multirod burst test program
- NCMART, algorithms and computer codes for a modified algebraic spatial reconstruction of spectroscopic emissivities for ELMO bump torus
- NRC antitrust licensing actions, 1978-1996
- National Coal Utilization Assessment : a preliminary assessment of coal utilization in the South : report to Assistant Secretary for Environment, Department of Energy
- National Library of Medicine toxicology data base : data management system
- National profile on commercially generated low-level radioactive mixed waste
- Neutral beam energy and power requirements for expanding radius and full bore startup of tokamak reactors
- Neutron exposure parameters for capsule 10.05 in the Heavy-Section Steel Irradiation Program tenth irradiation series
- Neutron exposure parameters for the dosimetry capsule in the Heavy-Section Steel Irradiation Program tenth irradiation series
- Neutron exposure parameters for the metallurgical test specimens in the sixth heavy-section steel irradiation series
- Neutron spectra at different high flux isotope reactor (HFIR) pressure vessel surveillance locations
- Neutron-photon multigroup cross sections for neutron energies <̲ 600 meV
- New FORTRAN computer programs to acquire and process isotopic mass spectrometric data
- New gamma-ray buildup factor data for point kernel calculations : ANS-6.4.3 standard reference data
- Next generation nuclear plant phenomena identification and ranking tables (PIRTs)
- Nondestructive fissile isotopic measurement technique for 233U-235U fuels using prompt and delayed fisson-neutron counting/
- Nondestructive inspection of plasma-sprayed metallic coatings for coal conversion equipment
- Nonlinear analyses for embedded cracks under pressurized thermal shock : comparisons with FAVOR and Weibull stress approaches
- Notch effects in uniaxial tension specimens
- Nuclear accident dosimetry : calculations and comparison with experimental data
- Nuclear air cleaning handbook : design, construction, and testing of high-efficiency air cleaning systems for nuclear application
- Nuclear criticality assessment of Oak Ridge research fuel element storage
- Nuclear criticality safety assessment of ORR, NBS, and HFBR fuel element shipping package
- Nuclear criticality safety of the fuel element fabrication facility at Attleboro, Massachusetts
- Nuclear cross sections for technology : proceedings of the International Conference on Nuclear Cross Sections for Technology, held at the University of Tennessee, Knoxville, TN, October 22-26, 1979
- Nuclear medicine technology progress report for quarter ending June 30, 1978
- Nuclear medicine technology progress report for quarter ending June 30, 1979
- Nuclear medicine technology progress report for quarter ending March 31, 1978
- Nuclear medicine technology progress report for quarter ending September 30, 1978
- Nuclear medicine technology progress report for quarter ending September 30, 1979
- Nuclear safety
- Nuclide importance to criticality safety, decay heating, and source terms related to transport and interim storage of high-burnup LWR fuel
- Numerical study of drift-Alfven waves in a sheared magnetic field
- OFFSCALE, a PC input processor for the SCALE code system
- OPUS/PlotOPUS, an ORIGEN-S post-processing utility and plotting program for SCALE
- ORCOST II--a computer code for estimating the cost of power from steam-electric power plants
- ORCULT-I, a loop dynamics simulator program for the core flow test loop
- ORNL coal chemistry, 1979
- ORVIRT.PC : a 2-D finite-element fracture analysis program for a microcomputer
- Oak Ridge Bicentennial Lectures : technology and society
- Oak Ridge Reservation annual site environmental report
- Oak Ridge Reservation environmental report
- Oak Ridge TNS program : reference design and program plan for a TNS ECH startup system
- Oak Ridge TNS program : study of fueling techniques in support of TNS development
- Offshore heat dissipation for nuclear energy centers
- One-dimensional model of fluidized bed combustor dynamics
- Optical diagnostics using a barium ion beam for spatial resolution of plasma parameters
- Owners of nuclear power plants
- PIE, a Fortran subroutine for plotting circles, concentric circles, pie charts and shaded pie charts
- POLIDENT, a module for generating continuous-energy cross sections from ENDF resonance data
- PR-EDB, power reactor embrittlement data base, version 1 : program description
- PUFF-III : a code for processing ENDF uncertainty data into multigroup covariance matrices
- Parametric study of the effect of burnable poison rods for PWR burnup credit
- Parametric study of the effect of burnable poison rods for PWR burnup credit
- Parametric study of the effect of control rods for PWR burnup credit
- Partial thermal denitration of uranyl nitrate solutions in a screw denitrator
- Performance evaluation of a low-first-cost, three-ton, air-to-air heat pump in the heating mode
- Performance of HTGR fuel in HFIR capsule HT-33
- Performance of triso-coated HTGR fissile fuel particles during in-block carbonization
- Pioneer women : pushing the frontiers of science and engineering at Oak Ridge National Laboratory
- Plan for development of an optimized PCRV for an HTGR power plant
- Poloidal magnetic field fluctuations in tokamaka
- Pool critical assembly pressure vessel facility benchmark
- Possible vulnerabilities of Cochin, India, to climate change impacts and response strategies to increase resilience
- Post-accident cleanup of radioactivity at the Three Mile Island Nuclear Station
- Postirradiation examination of recycle test elements from the Peach Bottom reactor
- Potential change in flaw geometry of an initially shallow finite-length surface flaw during a pressurized-thermal-shock transient
- Potential radiological impact of tornadoes on the safety of Nuclear Fuel Services' West Valley fuel reprocessing plant
- Potential safety-related pump loss : an assessment of industry data
- Power plant capital investment cost estimates : current trends and sensitivity to economic parameters, October 1979
- Precursors to potential severe core damage accidents : 1984 : a status report
- Precursors to potential severe core damage accidents : 1987 : a status report
- Precursors to potential severe core damage accidents : a status report
- Precursors to potential severe core damage accidents, 1986 : a status report
- Preliminary assessment of the fracture behavior of weld material in full-thickness clad beams
- Preliminary draft, environmental impact statement for hot engineering test project at Oak Ridge National Laboratory
- Preliminary neutronic analysis of a fast mixed-spectrum reactor (FMSR)
- Preliminary neutronic study of actinide transmutation in a fast reactor
- Pressure vessel safety research for advanced reactors : semiannual progress report for December 1991-March 1992
- Pressurized thermal shock probabilistic fracture mechanics sensitivity analysis for Yankee Rowe reactor pressure vessel
- Pressurized-water reactor internals aging degradation study : phase I
- Primer on durability of nuclear power plant reinforced concrete structures : a review of pertinent factors
- Probability-based evaluation of degraded reinforced concrete components in nuclear power plants
- Proceedings of a Workshop on the Evaluation of Models Used for the Environmental Assessment of Radionuclide Releases, Gatlinburg, Tennessee, September 6-9, 1977
- Proceedings of second annual Thermal Energy Storage Contractors' Information Exchange Meeting, September 29-30, 1977, Gatlinburg, Tennessee
- Proceedings of the Conference on Neutron Scattering : Gatlinburg, Tennessee, U.S.A., June 6-10, 1976
- Proceedings of the DOE/NRC Nuclear Air Cleaning Conference
- Proceedings of the IAEA Specialists' Meeting on Cracking in LWR RPV Head Penetrations : held at ASTM headquarters, Philadelphia, Pennsylvania, May 2-3, 1995
- Proceedings of the International Symposium on the Management of Wastes from the LWR Fuel Cycle : held at the Denver Hilton Hotel, Denver, Colorado, July 11-16, 1976
- Proceedings of the Joint IAEA/CSNI Specialists' Meeting on Fracture Mechanics Verification by Large-Scale Testing : held at Pollard Auditorium, Oak Ridge, Tennessee
- Proceedings of the Symposium on Potential Health and Environmental Effects of Synthetic Fossil Fuel Technologies, September 25-28, 1978 : first annual Oak Ridge National Laboratory Life Sciences Symposium
- Proceedings of the sixth annual Thermal and Chemical Storage Contractors' Review Meeting, September 14-16, 1981, Washington, D.C.
- Proceedings, Third Symposium, Training of Nuclear Facility Personnel, April 29-May 2, 1979, Gatlinburg, Tennessee
- Process options and projected mass flows for the HTGR refabrication scrap recovery system
- Production and testing of the revised VITAMIN-B6 fine group and the BUGLE-93 broad-group neutron/photon cross-section libraries derived from ENDF/B-VI.3 nuclear data
- Production control in HTGR fuel rod fabrication
- Production of high-energy chemicals using solar energy heat : project 8999 final report, for the period September 1, 1977 through May 31, 1978
- Progress in evaluation of radionuclide geochemical information developed by DOE high-level nuclear waste repository site projects
- Projection of light truck population to year 2025
- Protecting human subjects
- Pulse pileup effects on plasma electron temperature measurements by soft X-ray energy analysis
- QADS, a multidimensional point kernel analysis module
- Quarterly progress report on fission product release from LWR fuel for the period April-June 1976
- Questions and answers about EMF : electric and magnetic fields associated with the use of electric power
- Questions and answers based on revised 10 CFR part 20
- RASCAL 3.0 : description of models and methods
- RASCAL version 1.3 user's guide
- RLPORINC, the RELAP4/MOD5 interface to ORINC
- ROMOD, a code for control rod positioning
- Radial transport in the ELMO bumpy torus in collisionless regimes
- Radiant barrier attic fact sheet
- Radiation from Ag and K films bombarded by low energy electrons
- Radiation transport in earth for neutron and gamma ray point sources above an air-ground interface
- Radioactive waste disposal areas and associated environmental surveillance data at Oak Ridge National Laboratory
- Radioactive waste transportation systems analysis and program plan
- Recent capture cross section data from ORELA abve 2.6 keV
- Recent improvements in Thomson scattering : data analysis
- Recessed light fixture test facility
- Recommendations for the shallow-crack fracture toughness testing task within the HSST program
- Recommendations on fuel parameters for standard technical specifications for spent fuel storage casks
- Recommended electromagnetic operating envelopes for safety-related I&C systems in nuclear power plants
- Recovery of nonradioactive palladium and rhodium from high-level radioactive wastes
- Reflectors, infinite cylinders, intersecting cylinders and criticality
- Regional analysis of residential water heating options : energy use and economics
- Regional transportation energy conservation data book
- Reliability considerations for a coal-fired modular integrated utility system
- Reliability-based condition assessment of steel containment and liners
- Remarks delivered at the awards cerermony Fourth International Conference on Small-Angle Scattering of X-rays and Neutrons held in Gatlinburg, Tennessee, USA, October 3-7, 1977
- Report of the Task Group on Dose Calculations at the meeting of ICRP Committee 2, April 23-26, 1979, Harwell, England
- Report of the Task Group on Dose Calculations to ICRP Committee 2, March 17-21, 1980
- Report on aging of nuclear power plant reinforced concrete structures
- Report to the DOE Nuclear Data Committee
- Residential electric and gas water heaters
- Resolution of recurring loss alarms
- Results and analysis of the ASTM round robin on reconstitution
- Results of crack-arrest tests on irradiated A 508 class 3 steel
- Results of crack-arrest tests on two irradiated high-copper welds
- Review and prioritization of technical issues related to burnup credit for LWR fuel
- Review of ASME code criteria for control of primary loads on nuclear piping system branch connections and recommendations for additional development work
- Review of elastic stress and fatigue-to-failure data for branch connections and tees in relation to ASME design criteria for nuclear power piping systems
- Review of legal and institutional issues in the use of decentralized solar energy systems
- Review of reactor pressure vessel evaluation report for Yankee Rowe nuclear power station (YAEC no. 1735)
- Review of technical issues related to predicting isotopic compositions and source terms for high-burnup LWR fuel
- Round robins on the apparent thermal conductivity of low-density glass fiber insulations using guarded hot plate and heat flow meter apparatus
- SATDSK, a numerical simulation of the magnetic field due to saturated iron in cyclotron poletips
- SCALE, a modular code system for performing standardized computer analyses for licensing evaluation
- SEN wide-plate crack-arrest tests using A 533 grade B class 1 material : WP-CE test series
- SEN1, a one-dimensional cross-section sensitivity and uncertainty module for criticality safety analysis
- STARBUCS : a prototypic SCALE control module for automated criticality safety analyses using burnup credit
- Safety analysis report for packaging : the ORNL tungsten-shielded cask