Reactor Development Program. Progress Report, November 1967
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Pages: 172
Creation Information
Creator: Unknown. December 31, 1967.
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Argonne National Laboratory
Place of Publication: Illinois
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Physical Description
Pages: 172
Notes
Dep. CFSTI.
Subjects
Keywords
- Aarr
- Analysis
- Argonne Advanced Research Reactor/Beryllium Reflector For, Heat Transfer Analysis Of
- Atmosphere
- Atoms
- Beryllium
- Bismuth
- Bonding
- Boron
- Boron/Reactivity Worth As A Function Of Size
- Burnup
- Canning
- Carbides
- Carbon
- Ceramics
- Cesium
- Chemical Analysis
- Chromium Alloys
- Chromium Alloys And Systems/Cr--Ti--V, Mechanical Properties Of, Effects Of Neutron Fluence And Temperature On
- Control Elements
- Corrosion
- Critical Assemblies
- Critical Assemblies/ Reactivity Measurements For Small Sample Perturbations In Zpr-3 Fast
- Critical Assemblies/Atomic Concentrations Of Zpr-9 Assemblies 19-21
- Critical Assemblies/Core Material Samples For Zpr-3 Assembly 50 Fast, Specifications For
- Critical Assemblies/Mockup Of Fftf In Zpr-3, Composition Of Core For
- Determination
- Ebr-2
- Eigenvalues
- Electrons
- Expansion
- Explosions
- Fast Flux Test Facility/Core Composition Of, Nuclear Mockup In Zpr-3 Of
- Fast Neutrons
- Fftf- - Measurement
- Fluorides
- Frequency
- Fuel Elements
- Fuels
- Gallium
- Gallium/Fragmentation Of, Thermal Effects On
- Gallium/Fragmentation Of, Thermal Effects On N38100* --Power Reactor Development
- Getter
- Heat Transfer
- Heating
- Impurities
- Interactions
- Irradiation
- Jackets
- Liquid Metal Coolant
- Magnetic Materials
- Materials Testing
- Mathematics- - Measurement
- Mechanical Properties
- Meltdown
- Metals
- Mockup
- Molybdenum
- Molybdenum/Use As Burnup Monitor For Uranium Oxide Fuels, Feasibility Of
- Monitoring
- N38100* --Power Reactor Development
- Neutrons
- Numericals
- Oscillations
- Oxides
- Phosphides
- Plates
- Plutonium
- Plutonium Alloys
- Plutonium Alloys And Systems/Pu--U--Zr, Radiation Effects On, Postirradiation Analyses Of
- Plutonium Oxides
- Plutonium Oxides Puo$Sub 2$/ Puo$Sub 2$--Uo$Sub 2$, Fuel Pins Of, Electron Microprobe Analysis Of Irradiated
- Plutonium/ Separation From Spent Fuel, Use Of Fluoride Volatility Process For
- Power
- Preparation
- Pressure
- Production
- Programming
- Pyrolysis
- Radiation Effects
- Reactivity
- Reactor Core
- Reactor Fuel Elements/Radiation Effects On Carbide, Summary Of
- Reactor Fuels/Fragmentation Of Metallic, Dynamics Of
- Reactor Fuels/Pyrochemical Processes For Fast Oxide Breeder, Development Of
- Reactor Fuels/Sintering Of Oxide, Effects Of Atmospheric Conditions On
- Reactor Fuels/Stoichiometric Properties Of Oxide, Comparisons Of
- Reactor Safety
- Reactor Safety Experiments/ Sodium Loop Experiments In Treat, Analysis Of Metallic Fuel Meltdown In
- Reactor Safety Experiments/Fuel Meltdown Studies In Treat, Ceramic
- Reactors Analysis
- Reactors, Fast/ Fuels For, Preparation Techniques For Carbide
- Reactors, Fast/Dynamics Calculations For, Development Of Computer Codes For
- Reflectors
- Research Reactors
- Rods
- Ruthenium
- Ruthenium/ Separation From Plutonium Using Fluoride Chemistry
- Safety
- Separation Processes
- Sintering
- Sodium
- Sodium/Corrosion Inhibition In Liquid, Use Of Dissolved Getters For
- Stainless Steels
- Standards
- Stoichiometry
- Superheating
- Swelling
- Tantalum
- Tantalum/Reactivity Worth As A Function Of Size
- Temperature
- Testing
- Tin
- Titanium Alloys
- Titanium Alloys And Systems/Cr--Ti--V, Mechanical Properties Of, Effects Of Neutron Fluence And Temperature On
- Transfer Functions
- Traps
- Treat
- Tubes
- Uranium
- Uranium Alloys
- Uranium Alloys And Systems/Pu--U--Zr, Radiation Effects On, Postirradiation Analyses Of
- Uranium Carbides/Preparation Of Fast Reactor Fuels Of, Techniques For
- Uranium Compounds
- Uranium Dioxide
- Uranium Oxides
- Uranium Oxides Uo$Sub 2$/Puo$Sub 2$--Uo$Sub 2$, Fuel Pins Of, Electron Microprobe Analysis Of Irradiated
- Uranium Phosphides/Reactions With Jacketing Alloys
- Uses
- Vanadium Alloys
- Vanadium Alloys And Systems/ Cr--Ti--V, Mechanical Properties Of, Effects Of Neutron Fluence And Temperature On
- Vanadium Alloys And Systems/ Mechanical Properties Of Fuel Cladding Materials Of
- Variations
- Volatility Plutonium Alloys And Systems/Pu--U--Zr, Radiation Effects On, Postirradiation Analyses Of
- Zirconium
- Zirconium Alloys
- Zirconium Alloys And Systems/Pu--U--Zr, Radiation Effects On, Postirradiation Analyses Of
- Zpr-3
- Zpr-9
Source
- Other Information: UNCL
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Identifier
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- Report No.: ANL--7399
- Grant Number: W-31-109-ENG-38.
- Digital Object Identifier: https://doi.org/10.2172/4902466
- Office of Scientific & Technical Information Report Number: 4902466
- Archival Resource Key: ark:/67531/metadc1056441
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Office of Scientific & Technical Information Technical Reports
Reports, articles and other documents harvested from the Office of Scientific and Technical Information.
Office of Scientific and Technical Information (OSTI) is the Department of Energy (DOE) office that collects, preserves, and disseminates DOE-sponsored research and development (R&D) results that are the outcomes of R&D projects or other funded activities at DOE labs and facilities nationwide and grantees at universities and other institutions.
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Creation Date
- December 31, 1967
Added to The UNT Digital Library
- Jan. 22, 2018, 7:23 a.m.
Description Last Updated
- Jan. 30, 2018, 1:25 p.m.
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Reactor Development Program. Progress Report, November 1967, report, December 31, 1967; Illinois. (https://digital.library.unt.edu/ark:/67531/metadc1056441/: accessed May 27, 2024), University of North Texas Libraries, UNT Digital Library, https://digital.library.unt.edu; crediting UNT Libraries Government Documents Department.