Report containing "a discussion of the feasibility design and cost estimates for a gas cooled, natural uranium, graphite moderated power plant optimized for minimum power cost" (p. 3).

Report that contains "a preliminary design and feasibility studies of gas cooled, graphite moderated, nuclear power plants" (p. 1).

Fission gas holdup tests on the HRT charcoal beds under simulated operating conditions are complete. A radioactive tracer technique developed for use in laboratory absorption studies was utilized. The efficiency of the charcoal beds, in regard to holdup of fission gases, exceeds design specifications. On the basis of these tests, the charcoal beds should perform satisfactorily with the l#T operating at 10 Mw with a total oxygen flow of 3 liters/min. or at 5 Mw with a total oxygen flow of 3.5 liters/min., assuming that the maximum charcoal temperature in the first sections of the bed does not exceed 100 deg C and that the temperature in the 6 inch diameter section is in the 15 to 20 deg C range. (auth)

Heat transfer data are presented over a Reyuolds Number range of 400 to 8000 for the test fused salt Mixture No. 130 (62 mol % LiF-37 mol % BeFi-1 mol % UF/sub 4/ for a calibrating used salt Mixture No. 30 (50 mol % NaF--46 mol % ZrF/ sub 4/--4 mol % UF/sub 4/) flowing inside round heat exchanger tubes. A prelima- nary equation is developed for predicting shell-side heat transfer coefficients for liquid metal in turbulent, longitudinal flow over a square tube array having a pitch/diameter ratio of 1.165. An experimental value of the specific heat of fused salt Mixture No. 130 is also determined from the test data. (auth)

The following report records measurements and evaluations of fast neutron levels in remote areas monitored by personnel.

A study of the radiation effects of fast neutrons (O.5 ev to about 15 Mev) and gamma rays (fission spectrum) on various pieces of aircraft instrumentation is re ported. Components studied were: fuel gage vacuumtube amplifier and indicator, transistorized (germanium and silicon) servo amplifier system, and 4-in. diam. gyro. The fuel gage was subjected to a total neutron flux of about 6 x 1O/sup 5/nvt and about 5 x 1Osup 8/ r gamma with no adverse electrical effect. Physical damage was evident. Four transistorized amplifiers were irradiated in a fast flux of about 1.0 x 10/sup 10/cm/sup 2/ sec. Rapid loss in gain, rapid increase in d-c current drain, and complete failure occurred when the integrated flux reached about same flux. Studies on the gyro were inconclusive due to equipment failure. (auth)

Note presenting hot-wire anemometer measurements of the turbulent shearing stress in a turbulent boundary layer on a yawed flat plate. The measured velocity profiles are used to calculate the shear distribution and the result is compared with the result of experimental shear measurements.

Memorandum presenting an investigation to determine the operating characteristics of a small side-located control stick with the use of a ground simulator incorporating a power control system. The simulator or pitch chair was designed to produce the pitching motion associated with the short-period mode of an airplane. The general opinion of all of the pilots operating the pitch chair was that they were favorably impressed with their ability to precisely track with the small side-located controller provided the control-system characteristics were desirable.

Quarterly technical report discussing progress and activities of the Liquid Metal Fuel Reactor Experiment.

A frequency response analysis is made of the HRT fuel feedwater system. The characteristics of the components are determined and used in the differential equation of the system. Using frequency response techniques, theoretical calculations of static and dynamic response characteristics are made for reactor operation at 5 Mw. The conclusions arrived at as a result of this analysis include suggestions for improving the present operation. (auth)

The Homogeneous Reactor Test is designed for maintenance to be performed while the parts of the reactor are partinlly or completely submerged in water to reduce radiation levels. Tools with long handles permit the operator, standing above the equipment, to disconnect flanged joints, air lines, electrical and instrument leads, etc., in a minimum time. The techniques and tools employed to accomplish these various operations and to minimize intermixing of the contaminated process fluids with the shielding water are described. Estimates of shutdown times and costs of tools and spare parts are presented also. (auth)

The advantages, disadvantages, and cost of constructing a auclear power reactor underground are outlinedData on underground construction of hydroelectric plants, other structures, and underground reactor projects in Norway and Sweden are reviewed. A hypothetical underground Experimental Boiling Water Reactor design and sketch are given with cost estimates(T.R.H.)

Engineering study on underground construction of nuclear power reactors.

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Quantitative data on some of the variables affecting the performance of solid dry-film lubricants are presented. Included is a discussion of the test background, theory, methods used, sample pre-test treatment, and variables tested. (J.R.D.)

One of the major factors restricting reactor power levels is the incidence of ruptured slugs. The primary purpose in studying ruptures is to determine how reactor operating variables affect rupture rates. With this knowledge reactor operating conditions may be adjusted or controlled in the manner that will optimize reactor production. In addition, knowledge of rupture rate relationships are useful in fuel element development and in overall economic studies of existing and proposed reactors and reactor processes. This report is a compendium of various types of rupture information largely developed during the past eighteen months. Plant rupture experience for CY-1957 is reviewed; rupture rate correlations with reactor variables for solid natural uranium material are presented; a comparison between solid and cored natural uranium material rupture rates is made; the basis for current discharging practice of rupture-prone metal lots is discussed. 11 figs., 2 tabs.

Presented at ihe Ninth Meeting of the Supersonic Wind-Tunnel Assoc., Univ. of Southern Calif., and U. S. Naval Air Missile Test Center, Point Mugu, Calif., Apr. The Sandia 12 x 12-inch, transonic, blowdown tunnel facility is being equipped with a 10-channel digital datagathering system. The design and operation of ihe system are discussed. (W.J.H.)

The energy and angular distributions of the gamma rays leaking from the BSF reactor were computed by (((((((((Abstract unscannable))))))))))

The cost and feasibility of blending UNH streams of different uranium enrichments at HAPO was evaluated on a preliminary basis. Cases studied were blending 37.5% enriched UNH with depleted E metal UNH to yield a 0.947% enriched end product, and blending depleted E metal UNH with the depleted natural uranium to yield 0.7115% enriched end product. A reasonable degree of feasibility is indicated for such a blend program at HAPO.

The status of the various development projects associated with the Yankee Power Reactor is given. No data are reported. (For preceding period see YAEC-55.) (D.E.B.)

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Correlations based upon empirical modified equations derived from kinetic theory were developed for the thermal conductivity and viscosity of gas mixtures. The conductivity equation was compared to 226 binary mixture conductivities in temperatures from 0 to 774 deg C from the literature and this work. The average deviation is 2.1%. In correlating conductivity data of mixtures of polyatomic molecules, the energy transport is considered in two parts, i.e., one protion transferred by collision and the other by diffusion. The proposed viscosity equation reproduces 103 binary data points with an average deviation of 1.3%. These equations are more consistent with experiment than existing correlations in the literature. the relation of the conductivity or viscosity to composition and temperature are discussed in the light of the proposed equations. It has been demonstrated that, at a given composition, the ratio of the measured conductivity to that calculated on the molar average basis for mixtures of most simple molecules and the ratio of the measured viscosity to that calculated on the molar average basis for mixtures of most gases should be nearly constant over a temperature range of 200 to 300 deg C. The thermal conductivity of ten gases and selected binary and ternary …

From Introduction: " Considerable analytical and experimental research has been done to find means of reducing the noise levels of the turbojet transports. Noise levels can be decreased by engine redesign to reduce the jet-exit velocity (ref. 1), proper flight-climb techniques (ref. 2), and the use of noise-suppression exhaust nozzles (refs. 3 to 5). The present report is concerned with the last method."

Maximum HRT dome wall temperatures for reactor powers up to 10 Mw were calculated for both an insulated amd uninsulated dome. Temperatures exceeding 315 deg C in the fuel solution flowing through the HRT dome section can cause phase separation which results in excessive corrosion rates. The results, based on very conservative assumptions, inticated wall temperatures exceeding 315 deg C could occur in the insulated dome when operating the reactor at 10 Mw. Using the same conservative assumptions, the analysis of the uninsulated dome indicated wall and bellows temperatures below 300 deg C. (auth)