Search Results

open access

A PROGRAM OF RESEARCH ON MECHANICAL METALLURGY AS RELATED TO FUEL-ELEMENT FABRICATION. Quarterly Progress Report for the Period Ending June 30, 1961

Description: Results of crawing experiments using 3/8-in. bars to provide rod and tube test specimens are reported. In mechanical metallurgy investigations on the relation of formability to imperfection structure the peierls potentials for dislocation of Nb, Mo, Ta, and W were measured. Design and construction of a microextensometer reported. The investigations of the effects of grain size on the stored energy cold work were extended to a new lot OFHC Cu. In studies of formability relations with imperfection structure, a detailed study is reported on the internal-friction relaxation spectrum of Ta relatively unmodified by impurities. A summary of interstitial impurity effects on the internal-friction of Ta is given. (J.R.D.)
Date: August 31, 1961
Creator: Trozera, T Z; Koyama, K; White, J L & Chambers, R H
Partner: UNT Libraries Government Documents Department
open access

Magnetic Properties of Insulators. Quarterly Report No. 2 Covering Period May 15, 1961 to August 15, 1961

Description: The electron paramagnetic resonance (EPR) of color centers in additively colored KCl crystals is measured to observe the effects of optical bleaching at room temperature. Earlier measurements on the F-center are confirmed and the susceptibility is measured at 78 and 300 deg K over five decades of power, including the very low power region. The width and the saturation properties of the individual multiplets are studied in detail and the technique of making E PR measurements on inhomogeneously broadened lines is discussed. A calculation is presented which shows that a slight departure from a Lorentzian multiplet shape can account for the saturation data. The bleached crystals show a resonance which has a width of 35 gauss and a different rate of saturation than the F- center. This resonance is associated with the B-band which appears in the optical absorption. (auth)
Date: August 30, 1961
Creator: Markham, J. J.
Partner: UNT Libraries Government Documents Department
open access

Magnetic Properties of Insulators : Quarterly Report No. 2 Covering the Period from May 15, 1961 to August 15, 1961

Description: Abstract: "The electron paramagnetic resonance (EPR) of color centers in additively colored KCl crystals is measured to observe the effects of optical bleaching at room temperature. Earlier measurements on the F-center are confirmed and the susceptibility is measured at 78 and 300 deg K over five decades of power, including the very low power region. The width and the saturation properties of the individual multiplets are studied in detail and the technique of making EPR measurements on inhomogeneously broadened lines is discussed. A calculation is presented which shows that a slight departure from a Lorentzian multiplet shape can account for the saturation data. The bleached crystals show a resonance which has a width of 35 gauss and a different rate of saturation than the F- center. This resonance is associated with the B-band which appears in the optical absorption."
Date: August 30, 1961
Creator: Markham, Jordan J. & Noble, Gordon A.
Partner: UNT Libraries Government Documents Department
open access

MISCELLANEOUS EXPERIMENTS RELATING TO THE PROCESSING OF CETR FUEL BY SULFEX- THOREX AND DAREX-THOREX PROCESSES

Description: Experiments with unirradiated Consolidated Edison reactor ThO/sub 2/-- U0/sub 2/ fuel pellets indicated that uranium losses to Sulfex and Darex decladding solutions were proportional to the U0/sub 2/ content of the pellets. For example, after 7 hr, losses to boiling initial Darex solution (5 M HNO/sub 3/- -2 M HCl) were 0.45 and 0.65% from pellets containing 3 and 9% U0/sub 2/, respectively. The initial rate of dissolution of these pellets in 200% excess boiling 13 M HNO/sub 3/--0.04 M NaF-0.1 M Al(NO/sub 3/)/sub 3/ was essentially independent of the U0/sub 2/ content. Rates were 2.1, 3.0, and 2.4 mg min/sup -1/ cm/sup -2/ for pellets contdining 3, 6, and 9% U0/sub 2/, respectively. The presence in the dissolvent of the soluble neutron poisons H/sub 3/B0/sub 3/ and Cd(NO/sub 3/)/sub 2/ in concentrations up to 0.1 M and 0.075 M, respectively, had little effect on the rate of dissolution of sintered UO/sub 2/-- ThO/sub 2/ fuel pellets. (auth)
Date: August 30, 1961
Creator: Ferris, L.M. & Kibbey, A.H.
Partner: UNT Libraries Government Documents Department
open access

PERFORMANCE TESTS OF SNAP 10A THERMOELECTRIC ELEMENTS

Description: Apparatus for the performanee testing of SNAP 10A thermoelectric elements was designed, constructed, and is now in operation. Elements may be tested for any desired length of tfme up to 1400 deg F and in a vacuum of 1 x 10/ sup -5/ of Hg. The equipment used for these tcsts may also be utilized for measuring Seebeck coefficient and resistance as a function of temperature. Element performance is derived from the data on voltages and temperatures. The performance variables which are reported in graphic form are as follows: loaded output voltage at any desired DELTA T; open circuit output voltage at any desired DELTA T; power output under optimum load conditions; current produced under matched load conditions; and internal resistance of the element. (auth)
Date: August 30, 1961
Creator: Bergdorf, C.G.
Partner: UNT Libraries Government Documents Department
open access

Solvent Extraction of Uranium From Carbonate Solutions

Description: A process for recovering uranium from carbonate leach liquors by extraction with quaternary ammonium compounds was developed and evaluated in bench-scale continuous equipment with synthetic liquors. Uranium was recovered from the solvent by direct precipitation with sodium hydroxide --sodium carbonate solution. Results with relatively pure synthetic carbonate liquors were favorable, but attempts to treat a highly contaminated leach liquor from a western mill were relatively unsuccessful owing to interference from sulfate, chloride, thiocyanate, molybdenum, vanadium, and organic matter present. The process is therefore not considered competitive with the precipitation process used in several western carbonate-leach mills. (auth)
Date: August 30, 1961
Creator: Seeley, F. G.; Hurst, F. J. & Crouse, D. J.
Partner: UNT Libraries Government Documents Department
open access

Equations Representing Reactor System with Emphasis on KIB Digital Program

Description: "This report is written as a supplement to LAMS 2539. It is hoped that one will be able to read LAMS 2539, with emphasis on the fourth part (Memorandum N-4-79OU by 0. Farmer), with this memorandum to bridge the gaps and understand more about the model used and what the KIB Program can be used for. The system is defined by subsystems or subprograms: Thrust System, Heat Exchanger, Neutron Dynamics, Rod Actuator Dynamics, and Thermocouple Dynamics. The original Kiwi-B Flow System is included in the first part of LAMS 2539. This has been replaced by the newer system which includes a turbo-pump (per R, Bohl & E. Wheatley). This system will not be included here. Recommendations are made for improvement and more work in certain areas."
Date: August 29, 1961
Creator: Mohler, Ronald R.
Partner: UNT Libraries Government Documents Department
open access

The High-Temperature Chemistry of Fission-Product Elements. Summary Report, August 1, 1960-July 31, 1961

Description: A report is presented in which work on the hightemperature chemistry of the Cl--Rh systenm, the Cl--Os system, the Cl--Ru system, and the Cl--Pd is summarized. Other work is described on diffusion and kinetic effects in the transpiration method, and the chemistry of transition metal chlorides. (J.R.D.)
Date: August 29, 1961
Creator: Merten, U.; Bell, W. E. & Hale, J. D.
Partner: UNT Libraries Government Documents Department
open access

Physical property measurements on NPR graphite. II. Unirradiated core graphite

Description: Four bars of NPR core graphite produced by the National Carbon Company were evaluated. Thermal conductivity, electrical resistivity, coefficient of thermal expansion, tensile strength, compressive strength, and modulus of rupture data are summarized. Statistical analysis of the data was carried out. It is demonstrated that anisotropy in the bars and the method of sampling affect the measured properties. TSX is shown to be more anisotropic than either CSF or TSGBF graphites used in the construction of some of the present Hanford reactors.
Date: August 29, 1961
Creator: Jackson, J.L.
Partner: UNT Libraries Government Documents Department
open access

Report to the working committee

Description: Topics include: uranium quality and technology, fuel assembly technology, irradiation experience, E-N program, projection fuel program, overbore fuel program, Ni-plated Al-clad fuel elements, fuel element development, NPR program.
Date: August 29, 1961
Creator: Stringer, J. T. & Minor, J. E.
Partner: UNT Libraries Government Documents Department
open access

GAS-COOLED REACTOR PROGRAM. QUARTERLY PROGRESS REPORT FOR PERIOD ENDING JUNE 30, 1961

Description: Activities are discussed for research in design investigations, and materials development and testing conducted in connection with the development of the EGCR. The discussions are given in terms of: reactor physics; reactor design studies; heat transfer and fluid now investigations; materials development; in- pile and out-of-pile testing of components and materials; and development of test loops and components. (B.O.G.)
Date: August 28, 1961
Partner: UNT Libraries Government Documents Department
open access

Post irradiation examination of self support elements with severe in-reactor cladding corrosion (RM425)

Description: Three self support, natural uranium, I & E production fuel elements, which exhibited serious in-reactor cladding corrosion were selected from several tubes of discharged pieces from PT-IP-272-A-FP. The elements were transferred to the Radiometallurgy Laboratory for detailed examination to determine thickness of the remaining cladding and measure any irradiation induced dimensional changes in the fuel cores. Each element had four support tabs attached to each end and was from Parent Lot KT.009. The fuel geometry of all three was C IV NS.
Date: August 28, 1961
Creator: Gruber, W. J.
Partner: UNT Libraries Government Documents Department
open access

Post irradiation examination of transverse cracked rupture from 2986 DR (Rm 427)

Description: An O III N, I and E dingot element exhibited several transverse cracks when it failed in tube 2986 DR. Detailed examination in the Radiometallurgy Laboratory was requested to determine the cause of failure and obtain the ingot number. The element was so badly damaged that it was impossible to determine the exact cause of failure. Reaction between the coolant and fuel occurred at the internal surface around the spire over the total length of the element. Reaction was the greatest near the midpoint where the transverse cracks occurred and was least in the male end. Metallography of both longitudinal and transverse sections revealed that the metal quality of the fuel vas good. Cracks which originated from the oxide extended in both the longitudinal and transverse directions. The fuel near the core, which was insulated by oxide, was annealed but had not been heated into the uranium beta phase. One transverse crack which appeared to have water entry was observed approximately two inches from the male end. The ingot number was UZ 5751 B. After removal of the cladding at the ends, the uranium was bright dip etched and no defects were observed in the surface metal.
Date: August 28, 1961
Creator: Gruber, W. J.
Partner: UNT Libraries Government Documents Department
open access

A PROGRAM OF RESEARCH AND CALCULATIONS OF RESONANCE ABSORPTION. Final Report

Description: A direct numerical integration of the integral equation for the average collision density in the absorber was previously suggested in a discussion of resonance absorption. The implementation of this program is considered. The method of calculation, comparison with experimental data, and the computer code developed are described. The method of integration, computation of cross sections, selection of mesh size, integration interval, outside correction, the Dancoff correction, and unresolved resonances are discussed. Resonance integrals for U/sup 235/ and Th2/sup >/s3>s/sup 2/ were calculated and compared with experiment. (M.C.G.)
Date: August 28, 1961
Creator: Nordheim, L.W.
Partner: UNT Libraries Government Documents Department
open access

A Model for Fission-Gas Release From Porous Fuels in Low-Permeability Containers

Description: A simple mathematical model was developed to describe the steady-state release rate of gaseous fission products from porous ceramic fuels in low- permeability containers. The resulting equations are used to analyze experimental release rate results obtained from a UC/sub 2/-fueled graphite fuel body enclosed in a low-permeability impregnated graphite container. The relative release rates of the fission-product species Kr/sup 85m/, Kr/sup 88/, and Xe/sup 133/ were predicted with reasonable success. Absolute-rate predictions were not possible due to lack of information on true permeability and porosity profiles in the graphite container. (auth)
Date: August 25, 1961
Creator: Prados, John W.
Partner: UNT Libraries Government Documents Department
open access

Spectrographic Determination of Impurities in Hafnium

Description: A spectrographic method using d-c arc excitation in a controlled atmosphere was developed to analyze for seven impurity elements in radioactive hafnium samples. Analysis requires as little as 35 mg of hafnium oxide. (auth)
Date: August 25, 1961
Creator: Ginther, B. E. & Wheeler, G. V.
Partner: UNT Libraries Government Documents Department
open access

Hazards review Phase 1 fission product processing in B-plant

Description: Future operation of B-Plant for Phase I fission product processing involves may of the hazards associated with current chemical Processing Department activities in both the Purex and Redox Plants. The specific B-Plant hazards under Phase I operations are discussed in this report from the standpoint of comparable Purex and Redox hazards.
Date: August 24, 1961
Creator: Michels, L. R. & Zahn, L. L.
Partner: UNT Libraries Government Documents Department
open access

EVALUATION OF ULTIMATE DISPOSAL METHOD FOR LIQUID AND SOLID RADIOACTIVE WASTES. PART I. INTERIM LIQUID STORAGE

Description: As the first part of a study to evaluate the economics of the various steps leading to and including the permanent disposal of high-activity liquid and solid radioactive waste, costs of interim liquid storage of acid and alkaline Purex and Thorex wastes were estimated for storage times of 0.5 to 30 years. A 6- ton/day plant was assumed, processing 1500 tons/year of uranium converter fuel at a burnup of 10,000 Mwd/ton and 270 tons/year of thorium converter fuel at a burnup of 20,000 Mwd/ton. Tanks of Savannah River design were assumed, with stainless steel construction for acid wastes and mild steel construction for neutralized wastes. The operating cycle of each tank was assumed to consist of equal filling and emptying periods plus a full (or dead) period. With interim storage time defined as filling time plus full time, tank costs were minimum when full time was 40 to 70% of the interim storage time, using present worth considerations. For waste storage times of 0.5 to 30 years, costs ranged from 2.2 x 10/sup -3/ to 9.5 x 10/sup -3/ mill/kwh/sub e/ for acid wastes and from 1.7 x 10/sup -3/ to 5.1 x 10/sup -3/ mill/kwh/sub e/ for neutralized wastes. (auth)
Date: August 22, 1961
Creator: Bradshaw, R.L.; Perona, J.J.; Roberts, J.T. & Blomeke, J.O.
Partner: UNT Libraries Government Documents Department
open access

On Cratering: A Brief History, Analysis, and Theory of Cratering

Description: Cratering is a subject that has been studied by many investigators for many years for many purposes. These purposes range from experimental studies of physical properties to large scale excavations using explosive charges of kiloton size. In the past ten years considerable effort has been devoted to cratering experiments for the purposes of determining the effects of cratering by nuclear explosions, with recent accent on Plowshare applications. From the large amount of data available for craters in alluvian has been possible to establish very reliable relationships between charge size, depth of bursty crater radii, and crater depths. In addition it has been possible to construct a preliminary theory of the mechanics of explosive crater formation. The available experimental data for nuclear and high explosive craters are reviewed, with particular emphasis on the data for desert alluvium, and the pertinent relationships are derived. A theory of the important cratering mechanisms, which has been evolved on the basis of these data and data from other sources, is outlined. (auth)
Date: August 22, 1961
Creator: Nordyke, M. D.
Partner: UNT Libraries Government Documents Department
open access

Supplement A to design of PT-IP-263-A-FP, evaluation of chemically nickel plated fuel elements

Description: Irradiation of the initial test in this program involving ten tubes of alternately charged nickel-plated C-64 alloy clad test elements and X-80001 alloy control elements has been successfully completed. The test indicated that the nickel-plate spalling problem has been resolved, as no significant spalling or flaking was observed during the post-irradiation examination. The second test in this program will be to verify that the nickel-plate integrity problem has been solved by irradiating a pilot loading (up to 100 charges) of fuel elements which have been nickel-plated on a production basis.
Date: August 22, 1961
Creator: Clinton, M. A. & Hodgson, W. H.
Partner: UNT Libraries Government Documents Department
open access

Chemical Processing Department Monthly Report: July 1961

Description: This report, for July 1961 from the Chemical Processing Department at HAPO, discusses the following: Production operation; Purex and Redox operation; Finished products operation; maintenance; Financial operations; facilities engineering; research; employee relations; weapons manufacturing operation; and safety and security.
Date: August 21, 1961
Creator: Hanford Atomic Products Operation. Chemical Processing Department.
Partner: UNT Libraries Government Documents Department
open access

Radiochemistry for the rupture of Zircaloy-2 clad heavy-walled tubular fuel element in KER Loop-3

Description: On the 0000 -- 0800 shift, December 9, 1960, the delayed neutron monitor on KER Loop 3 gave a high coolant activity signal indicating a possible fuel element failure in this loop. KE Reactor was shut down immediately thereafter. This report is being written to summarize the events pertinent to this KE Reactor scram and to discuss the results and significance of data from analyses on coolant and coupon samples taken from the KER Loop 3 system.
Date: August 21, 1961
Creator: Perrigo, L. D.
Partner: UNT Libraries Government Documents Department
open access

12" SODIUM FLOW CONTROLLER. PERMANENT MAGNET COUPLING. MAGNETIC CALCULATION MANUFACTURE AND TEST RESULTS

Description: In order to retain the hermetic feature of the sodium flow controller, magnetic flux linkage of a permanent magnet coupling is used to transmit the torque produced by the operator through the pressure wall. Magnetic calculations, manufacture, and testing of this magnet coupling are described. (M.C.G.)
Date: August 18, 1961
Creator: Flator, H.E.
Partner: UNT Libraries Government Documents Department
Back to Top of Screen