Quarterly Status Report on the Advanced Plutonium Fuels Program, October 1-- December 31, 1967
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Pages: 55
Creation Information
Creator: Unknown. December 31, 1968.
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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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Los Alamos Scientific Laboratory
Place of Publication: New Mexico
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Physical Description
Pages: 55
Notes
Dep. CFSTI.
Subjects
Keywords
- Accessories
- Activation Analysis
- Analysis
- Bonding
- Breeding
- Carbon
- Carbon/Determination In Germanium And Stainless Steel By Helium-3 Activation Technique
- Ceramics
- Control
- Corrosion
- Criticality- - Cross Sections
- Crystals
- Defects
- Determination
- Diffraction
- Distribution
- Fast Neutrons
- Fission
- Fission Products
- Fission Products/Release And Distribution In Sodium Coolant From Plutonium Carbide--Uranium Carbide Fuel
- Fission Products/Release And Distribution In Sodium Coolant From Plutonium Carbide--Uranium Carbide Fuel N38700* --Reactor Components, Fuels & Accessories
- Fission Products/Yields From Fast Neutron Fission In Plutonium, Gamma Scanning Techniques For Measurement Of
- Fission Yield
- Fuel Cans
- Fuels
- Gamma Detection
- Germanium
- Heat Transfer
- Helium 3
- High Temperature
- Hydrogen
- Impurities
- Irradiation
- Lattices
- Liquid Metal Coolant
- Measurement
- N38700* --Reactor Components, Fuels &Amp
- Neutron Beams Reactor Fuels/Properties Of Ceramic Plutonium, Determination Of High Temperature
- Neutrons
- Neutrons/Effects On Fast Reactor Fuel Materials
- Oxygen
- Oxygen/Determination In Germanium By Helium-3 Activation Technique
- Oxygen/Removal From Sodium, Performance Of Cold Traps For
- Oxygen/Solubility In Sodium At 125 To 300--C
- Performance
- Plutonium
- Plutonium Carbides
- Plutonium Carbides/ Crystal Structure Of Room Temperature Pu$Sub 2$C$Sub 3$, Neutron Diffraction Determination Of
- Plutonium Carbides/Puc--Uc, Compatibility Of Sodium-Bonded, With Cladding Materials
- Plutonium Carbides/Puc--Uc, High Temperature Properties Of
- Plutonium Carbides/Puc--Uc, Preparation By Hydrogen Reduction Method
- Plutonium Nitrides
- Plutonium Nitrides/Pun--Un, Compatibility Of Sodium-Bonded, With Cladding Materials
- Plutonium Nitrides/Thermodynamic Properties Measurements On Pun
- Plutonium Oxides
- Plutonium Oxides Puo$Sub 2$/Puo$Sub 2$--Uo$Sub 2$, Preparation And High Temperature Properties Of
- Preparation
- Radiation Effects
- Reactivity
- Reactor Fuel Elements/Heat Transfer Properties Of Sodium-Bonded, Effects Of Bond Defects On
- Reactor Fuels/Compatibility Of Sodium-Bonded Carbide And Nitride, With Cladding Materials
- Reactor Fuels/Preparation Of Ceramic Plutonium
- Reactor Fuels/Properties Of Ceramic Plutonium, Determination Of High Temperature
- Reactor Fuels/Radiation Effects On Fast, Determination Of Neutron
- Reactors
- Reactors, Breeder/Physics Analysis Of, Evaluation Of Nuclear Data For
- Reactors, Fast/ Physics Analysis Of, Evaluation Of Nuclear Data For
- Reactors, Fast/Fuels For, Neutron Irradiation Effects On
- Reduction
- Sodium
- Sodium/Analysis For Impurities, Development Of Techniques For
- Sodium/Corrosive Effects On Fuel Cladding Materials At 650--C
- Sodium/Fission Product Distribution In, From Plutonium Carbide--Uranium Carbide Fuel
- Sodium/Quality Control In, Performance Of Cold Traps For
- Sodium/Solvent Properties For Oxygen At 125 To 300--C
- Solubility
- Stainless Steel-316
- Stainless Steel/Analysis Of Carburized, For Carbon By Helium-3 Activation Technique
- Stainless Steel/Corrosion Of Type 316, By Sodium
- Stainless Steels
- Standards
- Thermodynamics
- Transport
- Traps
- Traps/Performance Of Cold, For Impurity Control In Sodium
- Uranium Carbides
- Uranium Carbides/Puc--Uc, Compatibility Of Sodium-Bonded, With Cladding Materials
- Uranium Carbides/Puc--Uc, High Temperature Properties Of
- Uranium Carbides/Puc--Uc, Preparation By Hydrogen Reduction Method
- Uranium Dioxide
- Uranium Nitrides
- Uranium Nitrides/Pun--Un, Compatibility Of Sodium- Bonded, With Cladding Materials
- Uranium Oxides Uo$Sub 2$/Puo$Sub 2$--Uo$Sub 2$, Preparation And High Temperature Properties Of
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- Other Information: UNCL
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- Report No.: LA--3880
- Grant Number: W-7405-ENG-36.
- Digital Object Identifier: https://doi.org/10.2172/4903344
- Office of Scientific & Technical Information Report Number: 4903344
- Archival Resource Key: ark:/67531/metadc1058503
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Creation Date
- December 31, 1968
Added to The UNT Digital Library
- Jan. 22, 2018, 7:23 a.m.
Description Last Updated
- Feb. 5, 2018, 12:34 p.m.
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Quarterly Status Report on the Advanced Plutonium Fuels Program, October 1-- December 31, 1967, report, December 31, 1968; New Mexico. (https://digital.library.unt.edu/ark:/67531/metadc1058503/: accessed June 13, 2024), University of North Texas Libraries, UNT Digital Library, https://digital.library.unt.edu; crediting UNT Libraries Government Documents Department.