Abstract: Accurate measurement of OMRE fuel-element surface temperatures is important for evaluation of the performance of organic compound as moderator and coolant materials in nuclear reactors; a mixture of polyphenyls has been used in reactor operation to-date.

Abstract: The influence of plutonium on the nuclear characteristics of organic moderated cores is studied.

Abstract: A fuel material evaluation was made by destructively examining a full-scale experimental fuel element, irradiated in the SRE to a maximum of 850 Mwd/MTU.

Proposed fuel element loading and operating conditions for this test are tabulated. The loading is designed to provide high tube power and near-maximum-allowable coolant outlet temperature, accompanied by low fuel surface heat fluxes. Conditions which would exist during the proposed test were compared with those during the rapid depressurization incident in KER-2 on Jan. 31, 1960.

The rupture model presently being used by IPD Research and Engineering is the Weibull cumulative distribution function which in the region of interest, the model can be expressed approximately as: F(X) = failure rate in number of ruptures per total number of tubes, P = average tube power, T = average tube outlet temperature, M = exposure a{sub o}, a{sub 1}, a{sub 2}, a{sub 3} = parameters determined from rupture experience. F(X) = a{sub o}P{sup a1}T{sup a2}M{sub a3}. The parameters a{sub 1} = 3.3, a{sub 2} = 8.7, and a{sub 3} = 5 were estimated from experience with solid slug side-other and side-hot spot failures occurring from the spring of 1956 to the end of 1957, and were found to hold quite well for experience through 1958 as well. The model using the aforementioned estimates of the a{sub 1}, a{sub 2} and a{sub 3} parameters is being used in numerous ways, including fuel performance measurement (estimating values of a{sub o}, in essence), reactor optimization, project justification, production scheduling and forecasting, and fuel element test design. From time to time, doubt has been expressed about the appropriateness of applying these estimates of the a{sub 1}, a{sub 2} and a{sub 3} parameters, …

The purpose of this report is to provide scope and justification for the installation of one new 900 HP pump in the 181-D Building and to tie the two 36-inch headers together in order to supply sufficient water to increase production at 105-D and 105-DR.

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The viscosity of a liquid plutonium-iron eutectic alloy, which contains 9.5 atom per cent iron and melts at 411 degrees C, was determined up to 808 degrees C at Mound Laboratory by an oscillating cup viscosimeter. This type of apparatus employed a right-circular cylindrical cup containing the liquid under investigation attached to a torsion fiber. The dampening effect of the liquid upon the normal oscillations of the pendululm was a function of the viscosity of the liquid. The amplitudes of the oscillations of the pendulum were measured by a photographic technique. The periods of the oscillations were determined by an automatic timing mechanism. The reliability of the viscosimeter was demonstrated by following the expected function of the viscosity of liquid lead and bismuth over a larger temperature range than was previously reported.

The constitution of the plutonium-copper binary alloy as determined by differential thermal analysis is presented. The system is characterized by two congruent melting compounds, PuCu2 (m.p. 865 degrees C.) and Pu4Cu17 (m.p. 954 degrees C.); two incongruent melting compounds, PuCu4 (m.p. 906 degrees C.) and Pu2Cu11 (m.p. 926 degrees C.); three eutectics, 96 atom per cent copper (m.p. 626 degrees), 70.5 atom per cent copper (m.p. 849 degrees C.), and 91 atom per cent copper (m.p. 881 degrees C.); and two peritectics at 75 atom per cent (m.p. 906 degrees C.) and 85.5 atom per cent (m.p. 926 degrees C.). Solid solution was found above 97 atom per cent plutonium. The apparatus, the method of investigation, and the binary alloy phase diagram is discussed.

Abstract: A portable assembly for handling and shipping OMRE fuel elements is described and details of its operation are given. Problems of heat transfer and radiation shielding are discussed, and detailed analysis are presented.

Abstract: Tests were performed to determine the effect of thermal cycling on the across-the-seat leakage characteristics of commercially available valves considered for use in the sodium coolant system of the Hallam Nuclear Power Facility.

Abstract: This report describes a 300,000-kwe, sodium-cooled, graphite-moderated nuclear power plant based on existing technical information.

Ten experimental alloys of aluminum containing up to 4% nickel corroded uniformly, without intergranular attack, when exposed for 3 months to flowing deionized water at 260 deg C. The average penetration rates were between 1.4 and 1.9 mils per month. (auth)

A concept of a nuclear power plant to be assembled on earth and operated on the moon is presented. The two principal design objectives are reliability and high specific power. Wherever there is an incompatibility between these two objectives, the decision favors reliability. The design is based on the premise that the power plant must be designed on the basis of current technology and with a minimum amount of research and development. The principal components consist of a fast reactor in a direct cycle with a mercury-vapor turbine. The high- frequency generator, hydrogen compressor for the generator cooling system, mercury-recirculating pump, and condensate pump are on an extension of the turbine shaft. Ths mercury vapor is condensed and the hydrogen cooled in wing radiators. The reactor is of a construction quite similar to EBR-I Mark IlI for which there is a large amount of operating experience. The radiator is a vertical tube-and-fin type built in concentric cylindrical sections of increseing diameter. The curved headers are connected by swivel joints so that, upon arrival, the radiator can be quickly unfolded from the compact cylindrical package it formed during transportation. (auth)

Computational results for the characteristic values and solutions of Bessel's equation are presented. Specifically, the results pertain to the first two solutions subject to the Neumann boundary condition at r = a,b and to the first solution subject to the Dirichlet condition, when (b-a)/(b+a) is small (0.1, 0.01, and 0.001). Approximate analytic formulas are derived to complement the computational results. The possible application of the data to phenomena involving the interaction of an intense circulating beam and the electromagnetic fields within a particle accelerator is indicated, as is also the utility of the results for estimation of the loss-factor, Q, for resonant electromagnetic modes of possibly high order within a toroidal vacuum chamber of rectangular cross section. (auth)

Many of the experiments now being conducted on high-energy accelerators requires the use of beams of charged secondary particles. It is worth while at this time to attempt to summarize information about some of the most useful methods of setting up such beams. We are not concerned here with the primary beam of the accelerator. Rather, they assume that a target is struck by the primary beam and that it is desired to form a beam from the secondary charged particles that emerge from collisions within the target. The simplest system of forming this beam of secondary particles involves the use of magnetic fields only. In most cases it is desirable to obtain a beam of particles of known magnetic rigidity, or momentum. The bulk of this article is addressed to this problem. Some comments are also made about the use of electric fields in conjunction with magnetic fields. The inclusion of electric fields allows the separation of a beam of known momentum into its various components according to the velocities of the particles, hence according to the masses of the particles. These are referred to as ''separated beams''.

The engineering considerations are given on which the design and construction of tanks for the storage of low-level radioactive waste solutions were based. The tanks have a nominal capacity of 1,300,000 gal each. While conforming to the principle of total confinement, these tanks were built at a considerably lower cost than the tarks designed for storing high-level radioactive wastes. This saving was brought abeut by the elimination of a number of features such as cooling coils and the angular space and secondary saucer container around the tank. (auth)

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A multiple casting process was developed for the production of 0.590 plus or minus 0.005-in. diam. by 12-in. long solid right cylinders. The process involves vacuum induction melting in MgZrO/sub 3/ coated graphite crucibles and casting into coated graphite molds. Thirty-eight hundred fifty 90 wt.% U of 1.5 wt.% enrichment-10 wt.% Mo as-cast pins were produced for HNPF Exponential Experiments. (auth)

The Shippingport Atomic Power Station was operated for 715 EFPH from Ang. 11 to Oct. 7, 1959, in order to determine the performance characteristics reliability, stability, and lifetime variation of the core during rated power operation for an extended period of time. The plant was operated at successively lower power levels of 60, 43, and 17 Mwe to extend the Core I, Seed 1 lifetime. Logs and tables are included which present the events and all recorded data in this period. (D.L.C.)

The 9 single-crystal elastic moduli pertaining to principal crystallographic axes of alpha U at 25 deg C were determined from measurements of high-frequency wave velocities for 21 modes in seven single-crystal specimens, using the phase-comparison method of McSkimin. From the results the elastic compliances, compressibilities, and Poisson"s ratios were computed for the principal axes. Th variations with crystal direction of the stiffness moduli, Young's moduli, and rigidity moduli were plotted. The nature of the anisotropy for the different moduli indicated that the nearest neighbor interatomic bonds are considerably stiffer than the next nearest bonds, which are only slightly larger in interatomic distance. (auth)

Commercially available specimens of polycrystalline nand p-type lead telluride and n- and p-type bismuth telluride were irradiated in the Engineering Test Reactor. Total integrated flux times of 1.5 x 10/sup 20/ neutrons/cm/sup 2/ (thermal) and 1.6 x 10/sup 19/ neutrons/cm/sup 2/ (fast, i.e., for neutrons having energies greater than 1 (Mev) were accumulated by the specimens during irradiation. The specimen temperature during irradiation was 60 plus or minus 20 deg C. The effects of the irradiation on the thermoelectrical properties of these materials were found to be due almost entirely to fast neutrons insofar as most of the damage is healed during heat treatment. Increases in the electrical resistivity for irradiated n type PbTe and Bi/sub 2/Te/sub 3/ were found to anneal at temperatures below 200 deg C. Measurements of the electrical resistivity and Seebeck coefficient as a function of temperature for irradiated and unirradiated samples cut from the same ingot are given for all materials except p type PbTe. For the latter sample only the measurements of the Seebeck coefficient are given. (auth)

The TUT-T5 code for the IBM-704 estimates neutron capture probabilities in a one-energy, two-dimensional, rectangular cell model, using a Monte Carlo method. The problem and its solution are described in mathematical terms. The transport equation arising from the idealized physical model used in the code is derived and the problem is stated in terms of the solution of this equation. The validity of the Monte Carlo solution is established by proving that the random variables involved are unbiased for processes with convergent Neumann series. These random variables sum the distances travelled by randomly selected particle histories and use these sums to estimate flux integrals over the various regions. Capture probabilities are then obtained through multiplication by the appropriate capture cross sectione. The integrals which express the variances of these random variables appear too complicated to handle by analytic methods. (auth)

A micrometer that utilizes eddy current techniques is described. The gage is capable of measuring nominal 0.5000-in. aluminum rods to an accuracy of plus or minus 0.00005 in., and is unaffected by residual nonconductive surface filins such as oxides or corrosion products. (auth)