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Corrosion resistance and magnetic susceptibility (open access)

Corrosion resistance and magnetic susceptibility

From summary: "On the basis of the tests described herein, the corrosion characteristics of T-347 welded stainless steel are found not to be affected by the magnetic properties of the welds even though these properties are likely the result of the presence of the ferritic structure."
Date: March 7, 1949
Creator: Koenig, W. W. & Heckman, R. L.
System: The UNT Digital Library
Redox Process Chemistry: Freezing Point Data for UNH - NH₄NO₃ - HNO₃ - H₂O Systems (open access)

Redox Process Chemistry: Freezing Point Data for UNH - NH₄NO₃ - HNO₃ - H₂O Systems

Report presenting data on freezing point for UNH - NH₄NO₃ - HNO₃ - H₂O Systems. A range of concentrations of systems was used and data is presented.
Date: July 7, 1948
Creator: Harmon, M. K. & Cooper, V. R.
System: The UNT Digital Library
Boron stainless steel for drop rods (open access)

Boron stainless steel for drop rods

From introduction: "The present investigation of the properties of boron stainless steel is an outgrowth of a project started in 1947. The problem is to replace the present steel used for drop rods in the Hanford piles with a material much less subject to corrosive attack from the humid atmosphere existing at the location of the rods."
Date: September 7, 1948
Creator: Callen, A. C. & Heckman, A. L.
System: The UNT Digital Library
Improved Spectrographic Analysis of Uranium and Plutonium by the Carrier Concentration Method (open access)

Improved Spectrographic Analysis of Uranium and Plutonium by the Carrier Concentration Method

Introduction: "The carrier (pyroelectric) concentration method is commonly used in the spectrographic analysis of plutonium metal. This report describes work which lead to substantial improvements in accuracy, precision and ease with which the analysis is made. Included are data from analyses of plutonium metal by the original and the improved carrier methods, and the cupferron extraction method."
Date: October 7, 1952
Creator: Daniel, J. L.
System: The UNT Digital Library
Briquetting of machine plutonium turnings for recycle to the casting operation : final report - production test 235-6 (open access)

Briquetting of machine plutonium turnings for recycle to the casting operation : final report - production test 235-6

Report describing alternative methods for depleting a large turnings inventory in a short period of time.
Date: November 7, 1952
Creator: Chandler, B. A.; Peterson, R. E.; Lefevre, H. W.; Culvahouse, J. W. & Friesen, W. J.
System: The UNT Digital Library
A Rapid Method for Determining Preferred Orientation in Rolled Uranium Rods (open access)

A Rapid Method for Determining Preferred Orientation in Rolled Uranium Rods

Report covering an experiment on a method for determining the crystallographic orientation within uranium rods. From summary: "The crystallographic orientation existing in rolled uranium rods may be determined by comparing the diffraction pattern obtained from an unknown specimen with the diffraction pattern obtained from a sample known to be randomly oriented."
Date: January 7, 1953
Creator: Sanderson, M. J.; Cummings, W. V., Jr. & Hurst, R. P.
System: The UNT Digital Library
Field Handling Study of Heavy Aggregate Concrete (open access)

Field Handling Study of Heavy Aggregate Concrete

Purpose: "This test was conducted to gain information and experience in the handling of heavy aggregate concrete. The results from this test were to establish procedures for a subsequent program -- "Construction Test of High Density Concrete Shielding.""
Date: December 7, 1951
Creator: Emmons, C. D.
System: The UNT Digital Library
APDAC-I, A PCTR Data Analysis Code for the IBM 709 (open access)

APDAC-I, A PCTR Data Analysis Code for the IBM 709

A flexible foil data processing program is described. Raw data on foil radioactivity are the basic input information required. Output may consists of relative activities, saturated activities, and/or cadmium ratio and flux spectrum data. A statistical analysis of the data is executed with the direct calculation, and errors estimated for the output data.
Date: September 7, 1960
Creator: Lilley, J. R.
System: The UNT Digital Library
Analysis of Errors to be Expected in Measuring the Neutron Absorption Cross Section of C-12 (open access)

Analysis of Errors to be Expected in Measuring the Neutron Absorption Cross Section of C-12

An experiment now in progress should give some accurate information about the thermal neutron absorption cross section of carbon 12. This report outlines and summarizes this experiment and analyzes it to determine the main sources of error and the probably error in the final result.
Date: October 7, 1953
Creator: Seppi, E. J.
System: The UNT Digital Library
Rear Face Monitoring by Television:  Supplementary Report (open access)

Rear Face Monitoring by Television: Supplementary Report

Supervision and coordination of shutdown work are often made difficult by lack of visual contact between the front face, rear face and control room. Examples of such conditions are: Removal of process tubes, where close co-separation between front and rear elevator crews is required; Locating freshly discharged slugs accidently lodged on discharge face obstructions where radiation levels are high and optical viewing equipment inadequate; Monitoring of the transfer of hot samples from a process tube into a cask, where permissible exposure time is short and oral briefing of personnel who must perform subsequent operations is inadequate.
Date: December 7, 1953
Creator: Morris, W. J.
System: The UNT Digital Library
Experimental PRTR Moderator Flow Distribution Results (open access)

Experimental PRTR Moderator Flow Distribution Results

The moderator fluid will be injected into the PRTR calandrin through injectors located between the shroud tubes and at the bottom of the calandrin. It is important that the size and arrangement of the injectors be such that complete mixing of the moderator will occur and prevent hot sports from forming in the moderator. Such hot spots could lead to undesired changes in the moderating characteristics due to boiling within the moderator. Also of importance is the requirement that the injector should not produce excessive turbulence at the moderator surface thereby complicating moderator level control. To determine the extent of moderator mixing within the calandrin, experimental studies were made employing a full scale PRTR calandrin mockup.
Date: January 7, 1959
Creator: Kreiter, M. R.
System: The UNT Digital Library
Out-of-Reactor Tests on Pu-Al Type PRTR Elements for 1706-KER Testing (open access)

Out-of-Reactor Tests on Pu-Al Type PRTR Elements for 1706-KER Testing

The small amount of irradiation tenting experience on the plutonium-aluminum type elements planned for the Plutonium Recycle Test Reactor (PRTR) has made such testing of great importance. The high temperature pressurized recirculating water 1706 KER facility is one possible place for conducting investigations of the irradiation behavior of this type fuel element. To obtain the maximum information from the in-reactor testing and to detect possible problems, out-of-reactor test both at room and anticipated operating temperatures must be made. Room temperature pressure drop measurements and high temperatures performance of two prototypical fuel element designs proposed for KER testing are reported in this document.
Date: August 7, 1959
Creator: Doman, D. R.
System: The UNT Digital Library
Heat Transfer Testing (open access)

Heat Transfer Testing

Several tests are being performed and others being planned to investigate the role of heat transfer in corrosion processes. These tests are measuring both corrosion rates of metals (Zr-2 and X-8001 aluminum) under heat transfer, and the temperature rise associated with the buildup of the corrosion product. A brief description of these tests is given in this report.
Date: July 7, 1959
Creator: Doman, D. R.; Hokenson, J.F. & Lobsinger, R. J.
System: The UNT Digital Library
A Wrist Badge Film Dosimeter for Hand Dose Measurement (open access)

A Wrist Badge Film Dosimeter for Hand Dose Measurement

The wrist badge provides a dosimeter that is useful in estimating the radiation dose to the hands and forearms. Its new shield system gives good gamma and slow neutron dose discrimination with duPont 552 film packets. The film can be evaluated using the present technique and equipment. Several attempts to develop hand dosimeters have been made. Finger rings using film have been used routinely but have not been entirely satisfactory for all situations. The wrist badge was developed to provide improved gamma and slow neutron dose measurement of the upper extremities under certain appropriate conditions. The wrist badge dosimeter is not a substitute or alternate for finger ring dosimeters but is a necessary dosimeter for some extremity exposure situations.
Date: June 7, 1960
Creator: Bramson, P. E.
System: The UNT Digital Library
Scavenging as a Predisposal Treatment for NPR Decontamination Wastes (open access)

Scavenging as a Predisposal Treatment for NPR Decontamination Wastes

A disposal method is needed for wastes generated from the decontamination of the NPR primary coolant loop. The limitations imposed by facilities design criteria for the disposal of NPR wastes preclude direct river release of the spent cleaning solutions because of the anticipated quantities of radioactive material in these wastes. The soil at a 100-N Area trench or crib should not be relied on for removing radionucleotides by ion exchange or filtration because of the high salt content of the wastes and the presence of solubilizing reagents. Permanent or long term storage of large volume of decontamination wastes would be expensive. A waste treatment is sought for concentrating the radioactive materials to volume suitable for long term storage and which would permit dispersal of the excess liquid to the environs.
Date: June 7, 1960
Creator: Koop, W. N.
System: The UNT Digital Library
Process Improvement Transition Authorization #11-I Installation of Van Stone Seal Inserts - F Reactor. (open access)

Process Improvement Transition Authorization #11-I Installation of Van Stone Seal Inserts - F Reactor.

Continued operation of F reactor with high water collection rates during the past 12 years has resulted in numerous detrimental effects. In addition to promoting external corrosion tube leaks, water leaks have corroded the Gunbarrel to the biological shield donut assemblies and cast iron thermal shield blocks, thus preventing the majority of tubes in F reactor from unrestrained thermal expansion. Fatigue of the Van Stone flange under the resulting compression loads leads to eventual failure in some cases. In addition, excessive compression loads exerted against the nozzle gasket result in plastic deformation and eventual failures of the gasket.
Date: June 7, 1960
Creator: Russell, A.
System: The UNT Digital Library