31 Matching Results

Search Results

Technical activities report - July 1952 graphite development - pile graphite

Description: Physical data are presented for transverse CSF samples with capsule exposures of 568, 1049, and 1617 MD/CT. The higher exposures indicate a sharper damage gradient toward the front of the pile. Additional casings of various types of graphite were loaded into test holes during this month. Average values of the thermal conductivity and electrical resistivity for several types of virgin graphites are presented. Data of this nature will be a regular portion of this report henceforth. Process tube channel 2677-H was mined and traversed for bore diameter. Although several of the tube block junctions were obscured, the channel was quite uniform. Examination of all previously mined graphite powder samples for aluminum oxide corrosion product has been completed and the results are reported.
Date: August 11, 1952
Creator: Music, J. F. & Zuhr, H. F.
Partner: UNT Libraries Government Documents Department

100-K water plant facilities data for G.E. scoping

Description: This report discusses seven items related to the design of the 100-K water plant facilities. These items include: the number of process water connections to the reactor building, valving at the control building, and number of main pumping units; effect on heating system of the Hanford power outage during the winter period; reactor supply conditions; power requirements and steam flow at the local power plant; the service water system; general arrangement of the heat exchanger building; and pumping station control.
Date: August 8, 1952
Creator: Patterson, R.K.
Partner: UNT Libraries Government Documents Department

Improvement program -- 234-5 RMA Line

Description: After almost four months elapsed time since product introduction into the RMA Line, it was pertinent to evaluate both process and equipment performance and arrive at a program for future improvement. The suggestions and recommendations provided are those of the Technical Section. In those passages made to acknowledge the views of the appropriate groups.
Date: August 13, 1952
Partner: UNT Libraries Government Documents Department

Critical mass study of 231 process tanks

Description: An estimated minimum critical mass for each of the process vessels in the 231 Building has been calculated on the basis of critical mass data given in the P-11 Project Document HW-24514. The calculations are made assuming the plutonium to be a homogeneous mixture of precipitate and water with some slight neutron poisoning due to other elements. The precipitate is further assumed to have partially settled making an effectively infinite water reflector above the plutonium and hence reducing the critical mass.
Date: August 19, 1952
Creator: Lanning, D.D.
Partner: UNT Libraries Government Documents Department

Irradiation of 63S Aluminum Samples

Description: Data obtained from testing and observing samples of 63S Al irradiated for approximately three months are presented. Tensile data show a slight, general increase in strength during pile exposure with a slight decrease in elongation. It is uncertain whether tkis increase in strength is a result of irradiation, exposure to slightly elevated temperatures, or a combination of the two effects. Metallographic examination revealed no apparent damage to the microstructure. As a result of these tests. it was determined that there is no daruage in the 63S Al samples caused by irradiation. (auth)
Date: August 21, 1952
Creator: Wright, P. D.
Partner: UNT Libraries Government Documents Department


Description: The amount of Ac/sup 227/ per curie of Ra/sup 226/ was calculated for various values of neutron flux and various Irradiation times. The amount of Th/ sup 228/ produced per curie of Ra/sup 226/ and the percentage of Ac/sup 227/ converted to Th/sup 228/ relative to the total amount of Ac/sup 227/ produced were also calculated. (W.D.M.)
Date: August 28, 1952
Creator: Grove, G. R.; Russell, L. N. & Orr, S. R.
Partner: UNT Libraries Government Documents Department

Activation Energy for Fission

Description: The experimentally determined exponential dependence of spontaneous fission rate on Z{sup 2}/A has been used to derive an expression for the dependence of the fission activation energy on Z{sup 2}/A. This expression has been used to calculate the activation energy for slow neutron induced fission and photofission. The correlation with the experimental data on these types of fission seems to be quite good.
Date: August 29, 1952
Creator: Seaborg, Glenn T.
Partner: UNT Libraries Government Documents Department


Description: Progress is reported on the following projects: Th alloy development, mechanical properties of Th, tensile properties and preferred orientation of Th, triple-dip slug canning, texture studies, fundumental studies of alloying, static cerrosion tests with low melting point alloys, dynamic corrosion testing of fluoride materials, mass transfer, structures of liquid Pb and liquid Bi, fabrication of tubular laminates for fuel elements, creep of Th, cone-arc welding, Homogeneous Reactor Experiment metallurgy, a low-temperature specimen holder for use with the highangle x-ray spectrometers, metallography of Zr and its alloys, automatic polishing machine, a fuel element manufacturing process for the direct-cycle aircraft reactor, and fabrication of fuel and control rod elements for the MTR. (L.T.W.)
Date: August 28, 1952
Creator: Bridges, W.H. ed.
Partner: UNT Libraries Government Documents Department

Hydrogen Embrittlement of Zirconium

Description: The amount of hydrogen normally present in zirconium and zirconium alloys suffices to reduce their ductility greatly in an impact test at room temperature, after slow cooling from 6OO deg F. Quenching from 6OO deg F or above gives high impact strength, as does removal of hydrogen by hightemperature vacuum aanealing. The evidence on hydrogen embrittlement, the diffusion, solid solubility, and equilbrium pressure of hydrogen in zirconium the microstructure, and the effects of hydrogen and heat treatment on the mechanical properties of zirconium are discussed. (auth)
Date: August 22, 1952
Creator: Dayton, R.W.; Schwope, A.D.; Muehlenkamp, G.T.; Saller, H.A.; Dickerson, R.F.; Schwartz, C.M. et al.
Partner: UNT Libraries Government Documents Department

A High Vacuum High Speed Ion Pump

Description: A vacuum pump based on the properties of a magnetically collimated electric discharge is described. It has a speed in the range 3000 to 7000 liters a second and a base pressure in the order of 10{sup-6}mm.
Date: August 27, 1952
Creator: Foster, J. S., Jr.; Lawrence, E. O. & Lofgren, E. J.
Partner: UNT Libraries Government Documents Department

Recycle of 231 Building supernates to 224 T Building: Relationship to ``T`` and ``S`` Plant

Description: An examination of the process scheme for handling present and future 231 Building supernatant solutions is necessary to forecast the effects of placing one of the processing facilities (224B) in a standby status and to ascertain if rescheduling of any of the supernatant solutions to 202S will be necessary. The examination indicates the 231 Building process supernates and cell cleanouts together with the 221, 224T Buildings acid washes and the 234-5 Building returns can be processed through the 224 T Building as additions to regular runs or master recycle runs when T Plant is processing as much as 41.6 tons/month of 600 MWD/T material and S Plant is processing 120 tons/month of similar material. The processing rate through, 224 T Building to satisfy these conditions is seventy-six runs per month. This total is divided into 63 regular runs plus 13 meter master recycle runs. The number of master recycle runs are primarily dependent upon the T Plant rate in as much as only one master recycle is directly required for each 35 tons processed through S Plant.
Date: August 20, 1952
Creator: Packer, G. V. & Schmidt, W. C.
Partner: UNT Libraries Government Documents Department