Swaging of Uranium Dioxide Tubes - [Part] I (open access)

Swaging of Uranium Dioxide Tubes - [Part] I

Technical report. From Abstract: "A method was developed for fabricating tubular fuel elements of uranium dioxide by swage compaction of crushed, fused UO2. The elements were 5 to 10 feet long and were clad with stainless steel. UO2 densities up to 91% of theoretical were obtained in tubes about 2.1 inches in outside diameter and 0.3 inch in wall thickness."
Date: August 1960
Creator: Ferrara, Anthony S.
System: The UNT Digital Library
Automatic Dose Computer for Radiation Film Badges (open access)

Automatic Dose Computer for Radiation Film Badges

Technical report. From Abstract: "A combination densitometer and analog computer is described which determines radiation exposure of photographic film used in personnel badges. The range of the instrument is 0 to 300 mr gamma and 0 to 300 mrad beta plus gamma. A novel phototube circuit is used to obtain logarithms directly."
Date: April 1960
Creator: Davis, John E.
System: The UNT Digital Library
A Synopsis of Studies Related to Tritium Monitoring and Personnel Protective Techniques (open access)

A Synopsis of Studies Related to Tritium Monitoring and Personnel Protective Techniques

Technical report issued by E. I. du Pont de Nemours & Co. From Abstract: "Information obtained from investigations pertinent to tritium monitoring and protective measures at the Savannah River Plant are given. These findings were used to establish realistic protective techniques and consequently, to insure the safety of workers exposed to this hazard. Topics included are: contamination, permeation of plastics and rubber, instrumentation, and biological and physical aspects."
Date: February 1959
Creator: Butler, Harry L. & Van Wyck, Robert W.
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
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
A Detector for Sub-Surface Cracks (open access)

A Detector for Sub-Surface Cracks

From abstract: "An instrument was developed to detect cracks within 1/8 inch of the surface of cylindrical uranium fuel slugs. The instrument measures changes in eddy currents that are induced at a frequency of 2 KC."
Date: August 1954
Creator: Goodwin, L. E.
System: The UNT Digital Library
Sigma Plug Welding of Spun-Over Fuel Cans (open access)

Sigma Plug Welding of Spun-Over Fuel Cans

Summary: Purpose of the investigation is to improve the peripheral welding of the brazed joint at the top of aluminum-sheathed fuel slugs by forming the can over the top of the cap and welding the resulting center opening. This investigation looked at the applicability of the inert-gas-shielded, consumable electrode process, using commercially available equipment, for producing a weld closure in spun-over fuel cans. Using commercially available sigma welding equipment, no practical combination of welding conditions was found which resulted in satisfactory leak-tight closures in spun-over canned fuel slugs. It is recommended that plug welding of spun-over closures by the sigma welding process be dismissed from consideration for start-up at the Savannah River Plant.
Date: 1952
Creator: Winsor, F. J.
System: The UNT Digital Library
A Nonbound Detector for Hollow Slugs (open access)

A Nonbound Detector for Hollow Slugs

From abstract: "A tester was developed to detect nonbonded areas between the cladding and the core of hollow slugs. These slugs are one inch in diameter and eight inches long, and have a 3/8 inch axial hole. The tester employs an ultrasonic detector previously developed at the Savannah River Laboratory. A transducer 5/16 inch in diameter was developed to pass down the inside of the slug and a mechanical feeder was constructed to provide an automatic inspection cycle."
Date: October 1956
Creator: Ross, John D. & Leep, Richard W.
System: The UNT Digital Library
The Nuclear Test Gauge (open access)

The Nuclear Test Gauge

From abstract: "The 'Nuclear Test Gauge', a slightly subcritical assembly for quality control of reactor components, was designed, constructed, and placed in operation. calibration experiments demonstrated that the sensitivity of the unit is adequate, and that the speed of testing is increased y a factor of ten over that of a critical test pile."
Date: June 1956
Creator: Parkinson, Thomas F.; Goosey, Malcolm H.; Heston, William M. & Hollberg, Herbert J.
System: The UNT Digital Library
Ultrasonic Fusion Joining of Sintered Aluminum Powder Materials to Aluminum Alloys (open access)

Ultrasonic Fusion Joining of Sintered Aluminum Powder Materials to Aluminum Alloys

From abstract: "Essentially void-free fusion-type joints of high strength were produced between small specimens of Type M-276 sintered aluminum powder plate and 1100 Hl4 wrought plate, using a technique consisting of controlled and brief exposure of the ends of both materials to an ultrasonically active coupler face in a bath of molten 1100 aluminum, followed immediately by butt joining and fast cooling. With further development, the process should be adaptable to other types of sintered aluminum powder materials and to other joint geometries."
Date: August 1958
Creator: Thomas, John G. & Meyer, Florence R.
System: The UNT Digital Library
Fuel Meltdown Experiments (open access)

Fuel Meltdown Experiments

From Abstract: "Fuel tubes of enriched uranium-aluminum alloy were melted to various degrees of severity in the SPERT I reactor as a part of a program to evaluate reactor operating hazards. The heat flux encountered during the tests ranged from 200,000 to 650,000 pcu/(hr)(ft^2). The time required for the metal temperature to reach the melting point from the time when burnout began varied from 1.3 to 4.9 seconds. During these tests, pressure pulses were produced at a frequency of about one per second with peaks of about 150 psi."
Date: October 1958
Creator: Seaboch, James R. & Wade, James W.
System: The UNT Digital Library
Corrosion in Hydrogen Sulfide - Water Systems (open access)

Corrosion in Hydrogen Sulfide - Water Systems

From abstract: "This report gives a detailed account of the corrosion test work carried out by the Engineering Research Laboratory on the behavior of materials of construction in the hydrogen sulfide-water system. Results developed during the period from October 1950 through November 1954 are included."
Date: October 1955
Creator: Snyder, J. A. & Warren, D.
System: The UNT Digital Library