Fabrication of UO2 Fuel Elements by Vibrational Compaction (open access)

Fabrication of UO2 Fuel Elements by Vibrational Compaction

Technical report. From Abstract : "Arc-fused UO2 was vibrationally compacted to as high as 93.4% of theoretical density inside a stainless steel sheath tube. Selected particle sizes were used, and the assembly was vibrated axially in the frequency range of 300 to 1500 cycles per second. The same blend of UO2 particle sizes was vibrationally compacted to 87.5% of theoretical density within the annulus between two concentric stainless steel sheath tubes. The effects of particle size distribution, vibrational compaction procedure, sheath thickness, and fuel element shape on the maximum obtainable density were investigated."
Date: February 1962
Creator: Marah, Harold G.
System: The UNT Digital Library
Separation of Neptunium and Plutonium by Anion Exchange (open access)

Separation of Neptunium and Plutonium by Anion Exchange

Technical report. From Abstract : "The separation of neptunium and plutonium by anion exchange in nitrate solutions was studied under a wide variety of experimental conditions. A method of separation was developed that is adaptable to remote operation in the plant. In the method, Np(IV) and Pu(IV) are absorbed on an anion exchange resin from 8M nitrate solution. The column is washed with 8M HNO3 to remove contaminants; then the Pu is removed as Pu(III) by washing the column with HNO3 containing ferrous sulfamate and hydrazine. Finally, the Np is eluted with dilute HNO3."
Date: April 1962
Creator: Burney, Glenn A.
System: The UNT Digital Library
A Facility for Chemical Separation of Pu238 (open access)

A Facility for Chemical Separation of Pu238

Technical report. From Abstract : "A facility for separation of Pu238 and Np237 from irradiated neptunium dioxide target slugs was designed, constructed, and operated at the Savannah River Laboratory. This report describes the facility and includes design details of equipment." From Summary : "The main problems encountered during the design of the facility were: (1) to provide adequate containment and shielding of the radioactive materials, (2) to select chemical- and radiator-resistant materials, and (3) to provide for remote operation and maintenance of process equipment. ... This report contains a discussion of the major design problems and a detailed description of the facility and equipment."
Date: August 1962
Creator: Coogler, Arthur L. & Fowler, Bill F.
System: The UNT Digital Library
Formation of Hydrazoic Acid From Hydrazine in Nitric Acid Solutions (open access)

Formation of Hydrazoic Acid From Hydrazine in Nitric Acid Solutions

Technical report. From Abstract : "A study was made of the kinetics and stoichiometry of the formation of hydrazoic acid in nitric acid solutions containing hydrazine and ferrous sulfamate. The data were used to establish safe limits for the use of hydrazine in process solutions."
Date: September 1962
Creator: Dukes, E. Kenneth & Wallace, Richard M.
System: The UNT Digital Library
Chemical Processing of Pu238 (open access)

Chemical Processing of Pu238

Technical report. From Abstract : "Plutonium (principally Pu238) was separated from neptunium, and both the plutonium and neptunium were purified from fission products and cations by a three-cycle anion exchange process."
Date: October 1962
Creator: Tetzlaff, Ralph N.
System: The UNT Digital Library
Determination of Neptunium in High Activity Waste (open access)

Determination of Neptunium in High Activity Waste

Technical report. From Abstract : "An existing ion exchange method was adapted for use in a shielded facility to separate Np237 from highly radioactive solutions. The subsequent determination of neptunium was made by alpha counting and alpha pulse height analysis. The coefficient of variation was $.8% (n=10) for a synthetic sample and 5.9% (n=23) for plant samples."
Date: September 1962
Creator: Holcomb, H. Perry
System: The UNT Digital Library
Determination of Neptunium by Extraction With Tri-n-Octylamine (open access)

Determination of Neptunium by Extraction With Tri-n-Octylamine

Technical report. From Abstract : "An analytical method was developed for the determination of Np237 in solutions that contain plutonium and fission products. Np (IV) was extracted into tri-n-octylamine. A quantitative recovery of a Np237 standard was obtained with a coefficient of variation of 1.0% (n=10). A coefficient of variation of 3% was obtained for seven analyses of a process sample."
Date: September 1962
Creator: Britt, Robert D., Jr.
System: The UNT Digital Library