8 Matching Results

Search Results

Results: 1 - 8
open access

Creep of 2S-O Aluminum Sheet at 500 and 550 C

Description: Abstract: "Creep and creep-rupture tests were made on 25-O aluminum sheet at temperatures of 500 and 550 C. The estimated stresses that will produce 0.5 per cent deformation and rupture in 10,000 hours at 400, 450, 500, and 550 C (data at 400 and 450 C are from BMI-T-29, dated June 9, 1950) are presented."
Date: September 11, 1952
Creator: VanEcho, J. A.; Simmons, W. F. & Cross, H. C.
Partner: UNT Libraries Government Documents Department
open access

Properties of Stainless Steel-Uranium Dioxide Fuel Plates

Description: From abstract: "A method for fabricating 30-in.-long stainless steel - uranium dioxide sheet was developed and the properties of the fabricated sheet were investigated."
Date: May 11, 1954
Creator: Keeler, J. R. & Cuddy, L. J.
Partner: UNT Libraries Government Documents Department
open access

Further Studies on Large-Batch Melting of Uranium

Description: The following report focuses on an investigation made to determine if vacuum melting was an absolutely necessary step in the metallurgical process of melting and casting uranium.
Date: July 11, 1955
Creator: Rengstorff, George W. & Lownie, Harold W., Jr.
Partner: UNT Libraries Government Documents Department
open access

Fast-Neutron and Gamma Spectrum and Dose in Beryllium Oxide

Description: This report follows a series of tests run to determine the shielding properties of beryllium oxide, conducted at the Battelle Lid-Tank Shielding Facility. Neutron and gamma penetrations through and behind beryllium oxide were measured.
Date: January 11, 1961
Creator: Klingensmith, Raymond W.; Jung, Richard G.; Lindgren, William A.; Epstein, Harold M. & Chastain, Joel W., Jr.
Partner: UNT Libraries Government Documents Department
open access

Evaluation of Reactor Core Materials for a Gas-Cooled Reactor Experiment

Description: From introduction: "On February 1, 1956, Batelle was awarded a contract by the Army Reactor Branch (ARB) to select, develop, and test core materials which could be used successfully in conducting a Gas Cooled Reactor Experiment (GCRE). The prime objective of the GCRE would be to evaluate small portable reactor systems for military application...The present report is concerned with the GCRE activities at Batelle during approximately the 7 months' period following the first report of this series,… more
Date: July 11, 1957
Creator: Keller, Donald L.
Partner: UNT Libraries Government Documents Department
open access

Characterization of Inclusion in Dingot Uranium

Description: Abstract: The nonmetallic inclusions in both as-reduced and fabricated dingot uranium have been studied for comparison with those in ingot uranium. Special attention was paid to the hydride for the purpose of determining the amount and distribution in the various types of uranium. The types and distribution of other inclusions were also studied. It was found that the dingot uranium was of a higher quality than ingot uranium and was comparable to as-reduced derby uranium on the basis of over-all… more
Date: January 11, 1957
Creator: Cheney, Donald M. & Dickerson, Ronald F.
Partner: UNT Libraries Government Documents Department
open access

Theoretical Studies of the Solidification of Uranium Castings

Description: Report discussing a method of evaluating factors relevant to the creation of sound uranium castings. From abstract: "A mathematical model has been developed to calculate the time-temperature relationships in a cylindrical uranium casting during its solidification. Finite-difference equations are used, and the solution is obtained by use of a digital computer."
Date: July 11, 1958
Creator: Fletcher, Billie L.; Foster, Ellis L., Jr.; Franklin, Charles K.; Lechler, Andrew; Schwartz, Benjamin L. & Dickerson, Ronald F.
Partner: UNT Libraries Government Documents Department
open access

Development of Cermet Fuel Elements

Description: Abstract: "Fabrication techniques for making metal-ceramic fuel elements containing 60 to 90 volume per cent of UN or UO2 in a Type 302B stainless steel matrix was investigated. A hot press-forging procedure was most successful for fabricating fuel cores with a density of 90 per cent of theoretical or better. This procedure consisted of sealing the cold-pressed core compacts in stainless steel picture-frame packs, heating to 1900 F, and pressing to a total reduction in thickness of 35 per cent.… more
Date: August 11, 1958
Creator: Paprocki, Stan J.; Keller, Donald L.; Cunningham, G. W. & Kizer, Donald E.
Partner: UNT Libraries Government Documents Department
Back to Top of Screen