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Eurochemic Assistance Program: Progress Report for June, 1960 Through July, 1961

Description: The Eurochemic organization has been modified to include special contact groups for the architect-engineers. The current plant design capacity is 350 kg/day of natural uranium in aluminum or magnesium cladding and 200 kg/day of slight enriched uranium (5% max) in stainless steel and Zircoloy cladding. The processing of higher enrichment uranium (20 to 90%) is being considered. The pre-project design is essentially complete and projecting work has been started by three of the eight architect-eng… more
Date: August 31, 1961
Creator: Sloot, R. J.
Partner: UNT Libraries Government Documents Department
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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 imperfectio… more
Date: August 31, 1961
Creator: Trozera, T. Z.; Koyama, K.; White, J. L. & Chambers, R. H.
Partner: UNT Libraries Government Documents Department
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Storm Data and Unusual Weather Phenomena, Volume 3, Number 7, July 1961

Description: Monthly report containing a chronological listing, by state, of hurricanes, tornadoes, thunderstorms, hail, floods, drought conditions, lightning, high winds, snow, temperature extremes and other weather phenomena. It also provides information on storm paths, deaths, injuries, and property damage.
Date: August 31, 1961
Creator: United States. Weather Bureau.
Partner: UNT Libraries Government Documents Department
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Control Worth of B4C Rods

Description: This report considers the theoretical evaluation of a system for gaining increased control strength and increased control lifetime and presents a theoretical model which is applicable to conventional multigroup diffusion theory.
Date: August 30, 1961
Creator: Pomraning, G. C. (Gerald C.)
Partner: UNT Libraries Government Documents Department
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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 b… more
Date: August 30, 1961
Creator: Markham, J. J.
Partner: UNT Libraries Government Documents Department
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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 inhomog… more
Date: August 30, 1961
Creator: Markham, Jordan J. & Noble, Gordon A.
Partner: UNT Libraries Government Documents Department
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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 … more
Date: August 30, 1961
Creator: Ferris, L.M. & Kibbey, A.H.
Partner: UNT Libraries Government Documents Department
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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 gr… more
Date: August 30, 1961
Creator: Bergdorf, C. G.
Partner: UNT Libraries Government Documents Department
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Plan For VBWR Stability Experiment

Description: Stability tests are to be made in the VBWR (boiling water reactor). The tests are of three types: steady state measurements, rod oscillator tests, and transient tests.
Date: August 30, 1961
Creator: Cook, W. H.; Hodde, J. A.; Howard, C. L. & Niemi, R. O.
Partner: UNT Libraries Government Documents Department
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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 t… more
Date: August 30, 1961
Creator: Seeley, F. G.; Hurst, F. J. & Crouse, D. J.
Partner: UNT Libraries Government Documents Department
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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 th… more
Date: August 29, 1961
Creator: Mohler, Ronald R.
Partner: UNT Libraries Government Documents Department
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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
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LT-1, a General Reactor Lifetime Program for IBM-7090

Description: The LT-1 code calculates isotopic concentrations, absorption and fission rates, effective multiplication, and flux ration as a function of time for an infinite heterogeneous or homogeneous medium. A leakage correction if applied. Both equilibrium and batch loaded cycles are covered, and both thorium and U238 systems. Absorptions in control material are assumed at each point in time so that the flux ratios are always characteristic of the just-critical system.
Date: August 29, 1961
Creator: Preskitt, C. A. & Carlsmith, R. S.
Partner: UNT Libraries Government Documents Department
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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 construct… more
Date: August 29, 1961
Creator: Jackson, J.L.
Partner: UNT Libraries Government Documents Department
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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
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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
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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. … more
Date: August 28, 1961
Creator: Gruber, W. J.
Partner: UNT Libraries Government Documents Department
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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 midpoi… more
Date: August 28, 1961
Creator: Gruber, W. J.
Partner: UNT Libraries Government Documents Department
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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 reson… more
Date: August 28, 1961
Creator: Nordheim, L. W.
Partner: UNT Libraries Government Documents Department
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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 succe… more
Date: August 25, 1961
Creator: Prados, John W.
Partner: UNT Libraries Government Documents Department
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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
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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
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