Reactor Development Program Progress Report, September 1967
Physical Description
Pages: 155
Creation Information
Argonne National Laboratory December 31, 1967.
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This report is part of the collection entitled: Office of Scientific & Technical Information Technical Reports and was provided by the UNT Libraries Government Documents Department to the UNT Digital Library, a digital repository hosted by the UNT Libraries. It has been viewed 16 times. More information about this report can be viewed below.
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Argonne National Laboratory
Place of Publication: Illinois
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Titles
- Main Title: Reactor Development Program Progress Report, September 1967
- Serial Title: ANL Reactor Development Program Progress Report
Physical Description
Pages: 155
Notes
Dep. CFSTI.
Other Information: UNCL
Subjects
Keywords
- Activation
- Alkali Metals
- Alkali Metals/ Physical Properties Of
- Alkali Metals/ Physical Properties Of N38100* --Power Reactor Development
- Analysis
- Annealing
- Argonne Advanced Research Reactor/ Shielding For, Gamma-Heating Rates
- Argonne Advanced Research Reactor/Beam Tube Test Facility For, Description Of
- Argonne Advanced Research Reactor/Core Structures For, Thermal Analysis Of
- Argonne Advanced Research Reactor/Reflector For, Gamma-Heating Rate Distribution In Beryllium
- Beryllium
- Boiling
- Bubbles
- Building Materials
- Burnup
- Canning
- Carbides
- Chemical Analysis
- Chromium Alloys
- Configuration
- Containment
- Control
- Control Elements
- Corrosion
- Corrosion Protection
- Cp-6
- Creep
- Critical Assemblies
- Critical Assemblies/ Reactivity Measurements In Sodium--Plutonium Core Of Zpr-3, Perturbed
- Critical Assemblies/ Resonance Interaction Effects Measurements In Zpr-9
- Critical Assemblies/Doppler Effect Measurements In Plutonium-Fueled Zpr-3
- Critical Assemblies/Fuel Elements For Zpr-3, Foil- Activation Measurements Of Heterogeneity Effects In
- Cross Sections
- Cylinders
- Design
- Detection
- Determination
- Diffusion
- Distribution
- Disturbances
- Doppler Effect
- Ebr-2
- Elasticity
- Electromagnetic Fields
- Electrons
- Experimental Breeder Reactor-Ii/ Reactivity Measurements In, Effects Of Power Level On
- Experimental Breeder Reactor-Ii/Core For, Power And Isothermal Temperature Coefficients For
- Experimental Breeder Reactor-Ii/Hydraulic And Thermal Studies For
- Experimental Breeder Reactor-Ii/Operations History Of, Detailed
- Experimental Breeder Reactor-Ii/Sodium Coolant For, Chemical Analyses Of
- Failures
- Fast Neutrons
- Fission
- Fission Products
- Fission Products/Separation From Molten Salt Systems
- Flowmeters
- Fluid Flow
- Fluorides- - Fuels
- Foils
- Fuel Elements
- Fuel Pins
- Fuels
- Fused Salts
- Gamma Radiation
- Gamma Radiation/Absorption By Aarr Biological Shield And Beryllium Reflector, Heating Rate From
- Gases
- Gaskets
- Heat Transfer
- Heating
- High Temperature
- Hydraulics
- Impurities
- Instruments
- Interactions
- Irradiation
- Jackets
- Joints
- Liquid Metal Coolant
- Liquid Metals
- Liquids
- Magnetic Materials
- Manganese
- Mass
- Mass Spectrometers
- Mass Transfer/Facility For Studies Of High-Temperature, Description Of
- Materials Testing
- Measurement
- Mechanical Properties
- Metals
- Mixing
- Monitoring
- N38100* --Power Reactor Development
- Neutron Beams
- Neutrons
- Nickel
- Numericals
- Numericals- - Pressure
- Operation
- Oxides
- Plutonium
- Plutonium Alloys
- Plutonium Alloys And Systems/Pu--U--Zr, Radiation Effects On
- Plutonium Oxides
- Plutonium/Separation From Low Enrichment Fuels, Use Of Fluoride Volatility Process For
- Power
- Pressure
- Pulses
- Radiation Effects
- Reactivity
- Reactivity/ Measurements In Sodium--Plutonium Core Of Zpr-3 Of Perturbed
- Reactor Control Elements/Handling Of, Development Of Equipment For Remote
- Reactor Core
- Reactor Fuel Elements/Analyses Of Irradiated Pin-Type, Chemical
- Reactor Fuel Elements/Failure Detector For, Plugging Meter And Sampler For
- Reactor Fuel Elements/Radiation Effects On Clad-Metal Fuel
- Reactor Fuel Elements/Subassemblies Of, Design Of Instrumented
- Reactor Fuels/ Reprocessing Cycle For, Operation Of Anl
- Reactor Fuels/Radiation Effects On Oxide-Type
- Reactors
- Recovery
- Reflectors
- Remote Handling
- Reprocessing
- Research Reactors
- Research Reactors- - Resonance
- Resonance
- Response
- Rods
- Salts
- Sampling
- Seals And Glands/Mechanical Testing Of Gaskets
- Sensitivity
- Separation Processes
- Shielding
- Sodium
- Sodium/Corrosive Effects On Reactor Materials, Effects Of Temperature On
- Sodium/Purity Of, Development Of Methods For Controlling And Measuring
- Spectra
- Spectral Shift
- Stainless Steel-304-L
- Stainless Steel/Mechanical Properties Of Type 304L, Effects Of Exposure To Sodium On
- Stainless Steels
- Structural Materials
- Tellurium Fluorides Experimental Breeder Reactor-Ii/Core For, Power And Isothermal Temperature Coefficients For
- Temperature
- Testing
- Thermal Conductivity
- Thermal Neutrons
- Thermodynamics
- Time
- Titanium Alloys
- Transducers
- Transducers/Development Of Fission- Gas Pressure
- Transfer Functions
- Transport
- Tubes
- Uranium Alloys
- Uranium Alloys And Systems/Pu--U--Zr, Radiation Effects On
- Uranium Dioxide
- Uranium- - Uses
- Uranium/Separation From Low Enrichment Fuels, Use Of Fluoride Volatility Process For
- Uses
- Vanadium Alloys
- Velocity
- Voids
- Volatility
- Zirconium Alloys
- Zirconium Alloys And Systems/Pu--U--Zr, Radiation Effects On
- Zpr-3
- Zpr-9
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Identifier
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- Report No.: ANL--7382
- Grant Number: W-31-109-ENG-38.
- Digital Object Identifier: https://doi.org/10.2172/4902245
- Office of Scientific & Technical Information Report Number: 4902245
- Archival Resource Key: ark:/67531/metadc1056647
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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
- Nov. 11, 2024, 11:48 p.m.
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Argonne National Laboratory. Reactor Development Program Progress Report, September 1967, report, December 31, 1967; Illinois. (https://digital.library.unt.edu/ark:/67531/metadc1056647/: accessed January 22, 2025), University of North Texas Libraries, UNT Digital Library, https://digital.library.unt.edu; crediting UNT Libraries Government Documents Department.