This system will be undergoing maintenance May 24th between 8:00AM and 12:00PM CDT.

Search Results

open access

Short Time Strength Data for CS 1830 Series Cb-1Zr, Annealed at 2200F

Description: This technical report is a summary of short time strength data for CS1830 series Cb-1Zr material. The data are presented as a function of fabrication history or the amount of cold work received during fabrication. Three fabrication categories were considered for comparison: forgings and extrusions; bar, plate, rod and pipe; and sheet and tubing. Forgings and extrusions having received no cold work showed the highest strength over the entire temperature range 68F to 2800F; bar, plate, rod and pipe received moderate cold work and showed lower strength than forgings and extrusions but higher strength than sheet and tubing in the temperature range 2000F to 2800F.
Date: February 8, 1963
Creator: Watson, W. L.
Partner: UNT Libraries Government Documents Department
open access

Niobium-Tin-Aluminum Alloy Studies

Description: From Abstract : "A proposed constitutional diagram was developed from equilibrium data obtained for the niobium-tin binary alloy system. ... Alloying Nb3Sn with Nb3Al appears to raise the zero field superconducting transformation temperature of Nb3Sn slightly."
Date: February 1963
Creator: Ellis, Thomas Gordon & Wilhelm, Harley A.
Partner: UNT Libraries Government Documents Department
open access

Gamma Ray Efficiencies for Well Type Scintillation Crystals

Description: From Abstract : "Gamma ray efficiencies for various sized well type NaI(Ti) crystals have been calculated using an IBM 704 digital computer. The adjustable parameters in the program are the gamma ray energy, the heights and diameters of the crystal and the well, the thickness of the well lining, and the positions of the (point) source inside the well. Some typical results are presented in graphical form."
Date: February 8, 1963
Creator: Dingus, Ronald S. & Stewart, M. G.
Partner: UNT Libraries Government Documents Department
open access

Acid-Base Reactions in Fused Salts. Dichromate-Bromate Reaction

Description: Technical report. From Abstract : "The reaction of Lewis acid and base, Cr2O7= and BrO3_, in fused KNO3 - NaNO3 mixtures has been shown to involve an equilibrium followed by a slow decomposition to gaseous products."
Date: February 1963
Creator: Duke, F. R. & Schlegel, James
Partner: UNT Libraries Government Documents Department
open access

The Strontium-Strontium Hydride Phase System

Description: Technical report. From Abstract : "The Sr-SrH2 phase diagram was studied by thermal analysis, chemical analysis of equilibrated phases and X-ray diffraction. The maximum solubility of SrH2 in strontium metal is 38 mole % at the peritectic temperature of 880°C. Strontium metal undergoes an allotropic transformation at 555°C and melts at 768°C. A second transformation was found, at about 240°C, in samples containing hydrogen. Strontium hydride was found to have an allotropic transformation at 855°C."
Date: February 20, 1963
Creator: Peterson, D. T. & Colburn, R. P.
Partner: UNT Libraries Government Documents Department
open access

High Pressure Research at Low Temperatures

Description: Two principle reasons exist for the extension of high pressure research to temperatures near absolute zero. First, the comparison of certain data with theory (such as the pressure-volume relationship) is more meaningful if the effects of thermal vibrations can be ignored. Second, there are phenomena which can be studied only at low temperatures. These include superconductivity, the properties of solid helium and other inert gases, some electronic phenomena, etc.
Date: February 24, 1963
Creator: Swenson, C. A.
Partner: UNT Libraries Government Documents Department
open access

Reactor Branch monthly reports, January--December 1963

Description: This document details activities of the Reactor Branch during the months of January through December 1963. (FI)
Date: February 11, 1963
Creator: Plum, R. L.
Partner: UNT Libraries Government Documents Department
open access

NPR tritium production

Description: No Description Available.
Date: February 14, 1963
Creator: Baranowski, F. P.
Partner: UNT Libraries Government Documents Department
open access

Status of Harvey aluminum component evaluation: Production test IP-12-A

Description: About 298,000 OIIIN aluminum components were received from Harvey for evaluation after major steps were take in the vendor`s plant to upgrade product quality. This material met HAPO specifications and was comparable to Alcoa control components. Finished fuel elements (non-bumper and bumper) canned in the test and control components are tabulated by uranium core type and canning month. Non-destructive and destructive test data did not show any differences in clad fuel elements attributable to component quality. Irradiation status of non-bumper and bumper fuel elements clad in Harvey improved components as of Dec. 31, 1962, is tabulated, as is a summary of ruptures. It was recommended that Harvey Aluminum Co. be allowed to bit competitively on all future Al component orders except for the KVN and KVE component models.
Date: February 13, 1963
Creator: Blanton, W. A.
Partner: UNT Libraries Government Documents Department
open access

Test Results for Unrestrained Reactor, Gunbarrel-Nozzle Assemblies

Description: These tests were performed in accordance with a letter fran R. C. Breisch to J. R. Spink, May 7, 1962. An unrestrained gunbarrel condition was simulated for each of the standard process tube inlet assemblies for B,C and K type reactors. Primary objects of the testing were to obtain data on movement, pigtail damage, and effect on flow to the process tube in case of a Van Stone flange failure without key restraint of the gunbarrel. All test conditions were relative to actual conditions, but these conditions were not necessarily typical or maximum. The gunbarrels were not loaded with do-nuts or thermal shield pieces. All of the assemblies moved instantly and rapidly when released under pressure. The B and K braided type pigtails crimped just upstream of the ferrule on the nozzle connection. The helical tube C-type pigtail stretched about six inches, but did not travel far enough to cause flow restriction. Tube flow for the B case was 54 per cent of that prior to Van Stone flange failure. For the K test, the flow was reduced to 69 per cent of that prior to Van Stone flange failure.
Date: February 14, 1963
Creator: Goff, J. M., Jr.
Partner: UNT Libraries Government Documents Department
open access

Reactor instrumentation and safety circuit status review and program document

Description: This document has been prepared for internal use by the General Electric Company to serve as a program for evaluating reactor instrumentation and safety circuit equipment needs. It is intended that this document be used as a guide for defining, planning and scheduling engineering effort; budgeting of capital money; and project planning for new instrumentation systems. Effort will be made to periodically evaluate the status of the programs presented and provide updating information accordingly.After a plant has been built and operated for a number of years, it becomes apparent to operating and engineering personnel that certain modifications in controls and monitoring systems would provide both tangible and intangible benefits. Systems which were once thought to be the primary points of control shift in importance as others become recognized. As time passes this shifting spreads the main control focus from the central control desk to various other areas in the control room. Production rate increases cause instrument ranges and scales to be changed so that information on the process can still be obtained from existing equipment. Response times, sensitivity, limits, and time constants which were figured for one level must be used or revised for new levels. Further, it is discovered that the process monitoring points could be relocated or increased in number to provide more and better data on plant operation. New monitoring equipment is developed and installed to fill voids in information so production can continue meeting high standards for safety and process control. Equipment is fitted here and there in an already crowded control room, and some is even relocated to less advantageous positions to make available the necessary panel space. This in brief, is the rather complex status of Hanford Production Reactor instrumentation today.
Date: February 15, 1963
Creator: Deichman, J. L.
Partner: UNT Libraries Government Documents Department
open access

Interim report one to Production Test-IP-549-A, half-plant low alum feed water treatment at F Reactor

Description: A half-plant low alum water treatment test began at F Reactor on January 16, 1963 at startup from the scheduled January 3 tube replacement outage. The test, which was prompted by results obtained from a statistical analysis of fuel ledge corrosion attack, will demonstrate whether or not high alum feed is responsible for increasing the frequency of ledge corrosion attack on fuel element surfaces. The effect will be evaluated by comparing visual examination results obtained from normal production fuel irradiated in two different alum treated process waters. This report discusses the results obtained from twenty fuel charges, ten from each side of F Reactor, which were discharged prior to the reduction in alum feed to establish the pre-test corrosion environment.
Date: February 11, 1963
Creator: Clinton, M. A. & Geier, R. G.
Partner: UNT Libraries Government Documents Department
open access

Hanford Laboratories monthly activities report, January 1963

Description: This is the monthly report for the Hanford Laboratories Operation January 1963. Reactor fuels, chemistry, dosimetry, separation processes, reactor technology, financial activities, biology operation, physics and instrumentation research, operations research and synthesis, programming, and radiation protection operation are discussed.
Date: February 15, 1963
Partner: UNT Libraries Government Documents Department
open access

Production Test IP-560-A: Half-plant low dichromate, low pH water treatment at C Reactor

Description: This report details test plans for production test IP-560-A. The objective of which is to determine the corrosion effects resulting from reducing the amount of sodium dichromate corrosion inhibitor added to process water from 1.8 to 1.0 ppm at a process water pH of 6.6.
Date: February 18, 1963
Creator: Geier, R. G.
Partner: UNT Libraries Government Documents Department
open access

Chemical Processing Department Monthly Report: January 1963

Description: This report, for January, 1963 from the Chemical Processing Department at HAPO, discusses the following: Production operation; Purex and Redox operation; finished products operation; financial operations; facilities engineering; research employee relations; weapons manufacturing operation; and power and several maintenance operation.
Date: February 21, 1963
Creator: Hanford Atomic Products Operation. Chemical Processing Department.
Partner: UNT Libraries Government Documents Department
open access

Interim report 2: Production test IP-581-A half-plant high flocculation pH test at B Reactor

Description: A half-plant high flocculation pH test began at B Reactor on September 24, 1963. The purpose of the test was to determine whether operation of the water plant flocculation basins and filters at a pH higher than 7.0 with subsequent coolant pH adjustment to 6.6 is beneficial as far as radioactivity in the effluent is concerned. It is planned to increase the flocculation basin pH in steps to a maximum of 7.6. Although primarily an effluent activity test, fuel discharged after a metal cycle at each water plant condition will be monitored by visual examination. Thus, it will be possible to determine whether the incidence of localized corrosion is influenced by the various modes of operation. One 20 column fuel discharge, ten columns from each side of the reactor, was obtained prior to the start of the test. This report discusses the results obtained from the first discharge of fuel under test conditions.
Date: February 11, 1963
Creator: Geier, R. G.
Partner: UNT Libraries Government Documents Department
open access

Production reactor process tube film composition and radionuclide inventory studies. Status report

Description: The discharge of radioactivity from Hanford production reactors to the Columbia River has been studied for a number of years. The primary purposes of these studied have been to learn of the factors influencing production reactor effluent radioactivity concentrations and to develop methods for lowering the discharge concentrations of these radionuclides. In 1962 the Coolant Systems Development Operation (CSDO) began work on this program to determine the in-reactor film compositions and the inventory of radionuclides held in these films with the long-term objective of learning more about the complex in-reactor retention reactions that influence radionuclide effluent concentrations.
Date: February 12, 1963
Creator: Perrigo, L. D.
Partner: UNT Libraries Government Documents Department
Back to Top of Screen