30 Matching Results

Search Results

Advanced search parameters have been applied.
in subjects: "Mechanical Properties"  
Results: 1 - 24 next
open access

Hanford Laboratories Operation Monthly Activities Report: September 1957

Description: This is the monthly report for the Hanford Laboratories Operation, September, 1957. Metallurgy, reactor fuels, chemistry, dosimetry, separation processes, reactor technology, financial activities, visits, biology operation, physics and instrumentation research, and employee relations are discussed.
Date: October 15, 1957
Creator: Hanford Laboratories
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Fuel element performance

Description: For some time, it has been considered that cycling natural uranium fuel elements through the {alpha}-{beta} transformation point (approx. 662 C) is a contributing factor in split type ruptures. This hypothesis is based upon the fact that the transition temperature, a one percent increase in volume occurs. It is reasoned that as the uranium hardens under irradiation, it becomes progressively less able to adjust to the severe stresses imposed by the volume change as the material cycles through th… more
Date: December 31, 1957
Creator: Hagie, L. T.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Hanford Laboratories Operation monthly activities report, October 1957

Description: This is the monthly report for the Hanford Laboratories Operation. Metallurgy, reactor fuels, physics and instrumentation, reactor technology, chemistry, separation processes, biology, financial activities, employee relations, laboratories auxiliaries, radiation protection, operation research, inventions, visits, and personnel status are discussed. This report is for October 1957.
Date: November 15, 1957
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Hanford Laboratories operation monthly activities report, December 1956

Description: This is the monthly report for the Hanford Laboratories Operation. Metallurgy, reactor fuels, physics and instrumentation, reactor technology, chemistry, separation processes, biology, financial activities, employee relations, laboratories auxiliaries, radiation protection, operation research, inventions, visits, and personnel status are discussed. This report is for December 1956.
Date: January 22, 1957
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Hanford Laboratories operation monthly activities report, January 1957

Description: This is the monthly report for the Hanford Laboratories Operation. Metallurgy, reactor fuels, physics and instrumentation, reactor technology, chemistry, separation processes, biology, financial activities, employee relations, laboratories auxiliaries, radiation protection, operation research, inventions, visits, and personnel status are discussed. This report is for January 1957.
Date: February 15, 1957
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

DEVELOPMENT AND PROPERTIES OF URANIUM-BASE ALLOYS CORROSION RESISTANT IN HIGH TEMPERATURE WATER. PART IV. RADIATION STABILITY OF URANIUM-BASE ALLOYS

Description: The effects of pile irradiations on the physical properties and corrosion resistance of U-- Mo, U-- Nb; and U--Si alloys are reported. The dimensional stability under irradiation of the gamma phase U-- Mo and U-- Nb alloys is excellent; however, an isotropic volume increase of 4 to 6% per wt.% burnup may limit the ultimate fuel element life. Corrosion resistance of the gamma-phase alloys appesrs to be improved when subjected to s neutron field; this is attributed to an irrsdiation induced stabi… more
Date: May 1, 1957
Creator: Bleiberg, M.L.; Eichenberg, J.D.; Fillnow, R.H. & Jones, L.J.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

THE DEVELOPMENT OF COMPOSITE CONTROL RODS FOR WATER-COOLED POWER REACTORS

Description: The phrase "composite control rod" is used to describe a hafnium-tipped titanium-boron control component with a titanium cladding. Blades for such cortrol rods were successfully prepared in cooperation with the Battelle Memorial Institute by a picture-frame rolling technique. The rolling packs, which are machined from type 304 stainless steel, contain slntered titanium boron and wrought hafnium core materials in a commercially pure titanium envelope. Such packs are evacuated, sealod off, and ro… more
Date: October 15, 1957
Creator: Ray, W.E.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Semi-Annual Summary Research Report in Metallurgy for January-June 1957

Description: Study of the equilibrium phases which exist in Mg-rich alloys of the Mg-- U--Th system was continued. The precipitation of thorium as thorium dihydride from thorium-magnesium solutions was investigated over the temperature range 665 to 810 deg C. Soft, ductile niobium metal can be prepared by mixing essentially stoichiometric quantities of Nb/sub 2/O/sub 5/ and carbon, but slight deviation from stoichiometry yielded metal which was hard and non-ductile. The Zn vapor pressures over a number of Z… more
Date: December 20, 1957
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Radiation Damage to Graphite From 30 C to 185 C

Description: Property changes in polycrystalline graphite resulting from reactor irradiations at temperatures up to 185 deg C and over a range of exposures up to 1135 Mwd/ CT have been determined. Changes in stored energy, thermal conductivity, sample length, and C/sub O/ interlayer crystallite spacing are markedly decreased as exposure temperature is increased. Electrical resistivity changes are also less at higher exposure temperatures, but this property change does not depend as strongly on temperature a… more
Date: September 26, 1957
Creator: Nightingale, R. E. & Fletcher, J. F.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Analysis of Stresses and Deflections in Top Support Grid, PWR Reactor. Final Report

Description: The top grid of the PWR reactor core assembly is treated as a simply supported circular plate. The theory of plate is applied to the grid umder mechanical loads. The thermal stress problem is analyzed by treating the plate as under combined action of a laterally distributed load and forces in the middle plane of the plate. The load distribution is calculated from the temperature variation over the grid. The thermal stress problem then is equivalent to two problems: one, of bendimg of plate; and… more
Date: June 1, 1957
Creator: Yen, T. C. & Vining, R. E., Jr.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

CHARACTERISTICS OF THE SOLID STATE TRANSFORMATIONS IN-URANIUM

Description: The purpose of the investigation was to determine the temperature dependence of the lattice parameters of U from room temperature to the melting point and to provide experimental data on the general characteristics and kinetics of the allotropic transformations in U. Toward this end high-temperature x-ray diffraction, electrical resistance, and sonic experimental techniques were employed. The data presented are interpreted in terms of the known physical, mechanical, and structural properties of… more
Date: June 1, 1957
Creator: Klepfer, H.H. & Chiotti, P.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

FINAL STRESS ANALYSIS OF PWR SEED I, CORE I. Report No. 9561-3

Description: The structural analysis of the PWR Core 1 Seed 1 under prescribed thermal and mechanical loading with the object of predicting the structural reliability of the seed during actual service is described. Static and fatigue tests performed on fusion-welded Zircaloy specimens are described, and the results of these tests are incorporated in the reliability study. The applied stresses in the seed during operation of the reactor are quite low except at the end welds. Here, based upon the test data, a… more
Date: October 1, 1957
Creator: Mark, R.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Hydrogen Flammability Data and Application to PWR Loss-of-coolant Accident

Description: Supplemental to WAPD-SC-54l. A summary is presented of generalized data on the flammability of hydrogen in steam-air mixtures. The flammability data are applied to a postulated Pressurized Water Reactor loss-of-coolant accident and to estimates of the potential pressure effects on the PWR plant container. (C.H.)
Date: September 1, 1957
Creator: Shapiro, Z. M. & Moffette, T. R.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

BELLOWS FAILURE IN SOLIDS SEPARATION LOOP OF THE HRT MOCKUP

Description: The failure of the valve bellows would appear to be due to a combination of stress corrosion nnd crevice corrosion. Stress corrosion occurred as evidenced by the transgranular branched cracking found in the bellows and in the base which was joined to the bellows. It seems probable that chlorides were present, which, along with the residual stresses present in the bellows assembly, created the necessary conddtions for stress corrosion to occur. Crevice corrosion occurred probably due to heavy de… more
Date: February 1, 1957
Creator: Kegley, T.M. Jr. & Hammond, J.P.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

METALLURGY DIVISION ANNUAL PROGRESS REPORT FOR PERIOD ENDING OCTOBER 10, 1957

Description: High-Temperatare Metallurgy. A series of Inconel loops were operated to study the variation with time of depth of corrosion, effect of flow rate on corrosion, and effect of temperature drop on corrosion using fused salts. The corrosive effects of fused salts on Hastelloy B and Ni--Mo alloys are discussed. A series of Inconel--Na and Inconel-NaK forced circulation loops was operated to study the mass transfer in the systems. The mass transfer between Na and forced circulation loop of stainless s… more
Date: December 13, 1957
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Progress Relating to Civilian Applications During September 1957

Description: Data are given on the creep properties of Zircaloy-2 and Zircaloy-3 at elevated temperatures. Burst strength of welded Zircaloy-2 amd Zr tubes at elevated temperatures is given. A study of the effects of micronizing on UC/sub 2/ is presented. Some uranium corrosion rates in boiling solutions of electrolytes are given. Hardness amd grain-size dnta are given for Nb-alloy strips annealed one hour at 1500 deg C. Experiments are in progress to study the effects of applied bonding load amd the strain… more
Date: October 1, 1957
Creator: Dayton, R.W. & Tipton, C.R. Jr.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
Back to Top of Screen