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

Enriched ZrH/sub 1.65/ -2 wt.% uranium specimens were irradiated under 1 atm. of hydrogen at center-line temperatures between 900 to 1400 deg F to uranium burnups of between 13 and 25 at.%. Specially designed irradiation capsules were used to provide the conditions of temperature and hydrogen atmosphere which were required. Each capsule was instrumented with five thermocouples so that ample temperature data could be obtained during the irradiation. Almost negligible density changes were produced in the material by the irradiation. Changes in length and diameter were of a degree which could fall within experimental error in measurement. Metallographic examination showed no change in microstructure which could be attributed to the effect of irradiation. (auth)

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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.

Considerable interest has developed in the use of ion-exchange in the nuclear energy field in the last decade. Aside from the obvious use of providing demineralized coolant water for reactors, the projected uses of ion-exchange include the recovery of fission products from aquaeous waste streams and the separation and purification of fissionable materials from spent reactor fuels. The latter process may be incidental to the over-all operation, as is the case with the Purex anion exchange facility, or it may be the prime separation process, as may be the case in the recovery of Pu or U from spent power reactor (PRTR) fuel elements.

The purpose of the survey was to determine the radiation level in the Turbine Generator Services Building, around the Fuel Handling Canal, in the limited access areas of the reactor plant containers and on the boiler container roofs during plant operation. The test was performed with the plant at approximately 100 per cent power with three loops (1A, 1B, and 1C) in service. The radiation levels of the areas surveyed with a few exceptions were essentially background (.03 MR/HR). These exceptions were the Auxiliary Chamber and the limited access areas between the containers. The highest radiation level obtained in the survey was >2500 MR/HR at the reactor chamber walkway.

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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 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.

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 …

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.

Basic Studies. It has been reported previously that a reduction of PuO2 to a suboxide does not occur when a powder sample is heated for one hour at 1450 C. To investigate this anomaly, the present hooded facilities were converted from full air flow to an argon atmosphere to prevent oxidation of a possible suboxide. Five grams of PuO2 powder were heated in dry hydrogen to 1500 C for times of one and eight hours. Immediately after discharge, they were mounted and transferred to a helium atmosphere diffractometer hood. The resulting x-ray diffraction pattern consisted only of the single FCC PuO2 phase.

Report discussing the energy dissipated by fast electrons at different distances from monoenergetic electron sources, for plane perpendicular and point isotropic sources including tabulations and a summary of the theoretical methods and data utilized, and a table of spatial moments.

The Zircaloy-a clad, swaged UOa, 19-rod cluster fuel element for the PRTR was designed to use Zircaloy-a wire spirally wrapped around the fuel rods as spacing members. Such use of unbonded, Zircaloy-a spacers introduced the possibility of fretting corrosion. This paper reports preliminary irradiation tests conducted to determine whether or not such corrosions occurs in this fuel element design.

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)

The basic process for fabricating a swaged fuel rod is simple, easy to control and inexpensive. A zircaloy tube is filled with uranium dioxide powder, the ends temporarily plugged and the loaded tube is swaged to compact the UO2 powder to the required density. The swaged rod is then cut to length and counterbored and then end cape are welded into each end. After several tests and inspections, nineteen rods which meet the quality standards are assembled into a single fuel element ready for irradiation.

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 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."

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)

Abstract: The results of activity buildup studies in the SM-1 (APPR-1) performed from February 1958 to January 1959 are reported. Data are presented on the extent, nature, and mechanism of the buildup of long-lived gamma emitting nuclides in the reactor primary system. Mathematical equations to describe the activity buildup are derived. Radiation levels after reactor shutdown are presented, as well as the predicted radiation levels at the end of core life.

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.)

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.)

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 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.)