The performance of the Hallam Nuclear Power Facility heat transfer components was investigated in order to determine the steady-state, part load characteristics under various operating conditions. The complete steady-state temperature distributions, variations of flow rates and heat transfer coefficients throughout the sodium heat transfer systems as functions of reactor load are shown in a series of graphs. (M.C.G.)

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This document is the third in a series of progress report that records investigations of graphite bodies. Along with the report, two appendices are given to describe the different graphite bodies: "Synthetic Binders for Carbon and Graphite" and "High Temperature Physical Properties of Molded Graphites".

The objective of this test is to authorize irradiation of pilot quantities of alloyed dingot uranium and to provide for monitoring of its performance. This test will authorize: (a) Charging of up to 50 tons of alloyed dingot fuel elements in two groups of 25 tons each, including 12 monitor charges which will accompany the first group, into D Reactor as a pilot loading. Although purer and ore dense than standard ingot uranium, the dingot uranium produced in the past by MCW has demonstrated poorer dimensional stability during irradiation. The instability has been manifest as warp, nearly double that of ingot which was irradiated in the same charge and by surface bumping up to 5 mils in height. Both the bumping and the warp are normally associated with large grain size, non-uniform orientation and/or residual stresses. To improve the stability,, primarily by grain size reduction, additions in the range of 150 ppm iron and 100 ppm silicon are being made to the green salt prior to reduction. The hydrogen content of the metal has been reduced by pre-heating the green salt at high temperature prior to triggering the metal reduction. Further refinements to the process include heat treatment in chloride …

The objective of this production test authorization is to permit the irradiation of sixteen, 0.394 inch diameter, metallic uranium spheres at temperatures between 300C and 800C in the 3674 ank 3865 KW front-to-rear test tubes. Eight spheres will be of natural uranium and eight of enriched (3% U-235) uranium. Temperature controlled and temperature monitored test capsules containing either four natural or three percent enriched uranium spheres will be irradiated. Pre- and post -irradiation examinations will be performed to determine the extent of swelling. The temperature of the spheres will be controlled at the same constant level during reactor operation and during shutdowns. Capsule exposures will vary from one to 24 months. This production test authorization will permit the irradiation of two capsules each containing four natural uranium spheres and two capsules each containing four three percent enriched uranium spheres.

Document issued by the Office of the Attorney General of Texas in Austin, Texas, providing an interpretation of Texas law. It provides the opinion of the Texas Attorney General, Will Wilson, regarding a legal question submitted for clarification: Constitutionality of H.B. No. 43, 56th Legislature, levying a tax to be known as the "Severance Beneficiary Tax."

An evaluation was made of the use of NaK as the primary coolant for the SNAP-2 system. Pumping-power limitations based on the mercury Rankine cycle are analyzed. Problems pertinent to any design-specification modifications are reviewed.

Abstract: Ground effects resulting from Blanca, Logan, Evans, Tamalpais and Mars events of HARDTACK Phase II underground explosions were measured by strong-motion and teleseismic seismographs out to distances of nearly 100 miles.

The angular relationships of warp to rib marks and warp to hot spots were measured for a large number of fuel elements. The data was analyzed and found to provide information regarding the formation of warp and hot spots.

The Palmolive program is directed toward the recovery of neptunium-237 and production of plutonium-238. The neptunium is recovered during the chemical processing of irradiated uranium and is purified and fabricated into target elements. The target elements are irradiated to produce plutonium-238 by neutron capture of neptunium-237 and are processed to provide plutonium for shipment to the final customer and neptunium for recycle within the system. This report summarizes a preliminary engineering study of the technical and economic factors involved in installing long-term Palmolive manufacturing facilities at Hanford to meet the reduced production goals. Prime emphasis is placed on the process technology and plant equipment requirements for fabricating and reprocessing neptunium target elements on a production basis. The relationships of these phases of the target cycle to the recovery and purification of virgin neptunium in the Purex Plant and irradiation of target elements in the Hanford reactors are reviewed in the light of the reduced plutonium-238 demands.

The purpose of this report is to present the results of a brief series of transient heat transfer experiments directed toward determining the possibility of damage to a K reactor should a front hydraulic connector fail to a tube containing I&E fuel elements. Nuclear heating of a train of 32 I&E slugs was simulated by electrically heating a rod in a K geometry process tube. Failure of a front fitting to such a tube was simulated by simultaneously and rapidly closing a valve in the water supply to the tue and opening a valve in a line which permitted discharge from the inlet of the tube through a front nozzle to atmosphere. Two to three seconds after the valve operation, a power reduction was initiated. The power reduction was in accord with an 800 inhour scram, except for two runs at 1,500 inhours. The reverse flow, rear header pressure and eight rod thermocouples, as well as other less important variables, were monitored. A test was continued until rod temperatures of 450 to 500 C were reached or until conditions of adequate cooling were established. With the exception of one run at 750 KW, all runs were with an initial tube …

From summary: This report summarizes the work performed in a brief study made for the AEC of boiling water reactor power plants in the 5 to 40 eMW output range.

Foreword: In early 1959 the U.S. Atomic Energy Commission initiated a study to assess the feasibility of low-level power generation through the use of certain types of small-sized nuclear reactors.

A progam to determine the effect of variations of Al content, heat treatment, and basic slip mechanism upon room temperature ductility of Fe--Al alloys is reported. (W.L.H.)

It has been the custom to report the operating experience at the ORR along with other activities in the reports of the ORNL Operations Division. It was decided to combine the sections of the Operations Division reports appropriate to ORR operation covering the year from April 1958 through March 1959. (W.D.M)

A study was conducted to develop equations for calculating fission product heating in the RRT-CP undeflow pot from measured temperatures and to attempt to correlate the rate of solids accumulation in the undeflow pot with flssion heating and reactor power. Using fission heating data calculated from the heat balances developed, several semi-empirical equations relating solids accumulation and heating were tested. In one case an error of no greater thaQ 26% was incurred in the calculation of the total weight of solids collected during chemical plant runs 17-4, 17-5, and 17-6. Further development work will be done on this correlation. (auth)

The basic principles of scintillation counting are reviewed. The design, performance, and operation of a placed on instruments ior medical uses. (C.H.)

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A method was developed for using an IBM-650 data processing machine to obtain detailed information concerning thermal and hydraulic conditions within a platetype reactor channel when the coolant in the channel is present in both vapor and liquid phases. (auth)

The objective of the program is to determine the effect of variations of Al content, heat treatment, and basic slip mechanism upon the room temperature ductility of Fe - Al alloys. Additional heat treatment studies on 13.9 Alfenol tends to confirm earlier observations that reproducibility of ductility values of 8 to 9% are difficult to obtain. The preparation of Al - Y - Fe, and Al - Mo - Y - Fe alloys by arc melting in a non-consumable electrode arc furnace is reported. A resistivity versus temperature curve for the 13.9% Al alloy containing 1% Mo was determined. (W.L.H.)

From abstract: "A study is made of various processes that occur prior to the pinch effect when an electric field is applied to a deuterium gas. The variables of the problem are percentage of ionization, the electron and ion temperatures, the resistivity of the gas, and the current density."

A method for determining the concentration of Li6 in aqueous solution has been tested using the nuclear reactions Li6 (n,α)H3 and O16 (H3,n)F18. Annihilation 7 radiation of induced 1.87 hour F18 radioactivity was counted with a well-type scintillation counter, and the radioactivity per millimole of lithium was found to be independent of lithium concentration below about 0.2moles/liter. The sensitivity limit for detecting lithium is less than 0.1 micromole (0.0075 micromole Li6).

The thermodvnamic and transport properties of gaseous CO/sub 2/ are presented. The properties were coruputed from the most recent data. The results are presented graphically with pressure and temperature as independent variables for convenience in engineering calculations. (J.R.D.)

Neutron multiplication measurements were made on a number of cylindrical assemblies of Pu and graphite disks. S/sub n/ calculations were made on homogeneous mixtures of Pu and graphite with varying C/Pu ratios and varying reflector thickness. (auth)