A report regarding a survey of the condition of wells and springs in the Rio Blanco County, in N.W. Colorado.

Annual report describing progress on unclassified research programs funded by the U.S. Atomic Energy Commission during the 1964-65 fiscal year.

From abstract: Project Dugout was a chemical explosive row charge cratering experiment in hard rock conducted at the AEC Nevada Test Site as part of the Plowshare Program for development of nuclear excavation technology.

Observation of the long-term effects of weathering on 10 nuclear craters over periods as long as 12 years.

Report evaluating the design characteristics and limitations of mobile blankets for breeder reactors. This also includes economic considerations for each tested blanket. Appendices begin on page 40.

Technical report. From Abstract : "A system has been developed to program a digital computer in much the same manner as an analog computer is programmed. Properties of a general purpose analog computer and a digital differential analyzer are combined to yield a program which employs, as input, standard data cards prepared from a diagram analogous to an analog computer diagram. The capacity of the system is much greater than that of most analog computers, making it applicable to large simulation problems. No scaling is required. The system is compatible with the Fortran symbolic language and may be used as part of a larger digital computer program. It may be applied to the more general types of boundary value problems arising in process simulation in addition to the initial value problems ordinarily solved on analog computers. It is particularly well adapted to non-linear problems and to control problems involving large transport delays. The program operates in basic machine language and, when used by itself, requires no compilation time."

In-pile loop experiments L-2-15 and L-4-16 were two of a series designed to test the radiation corrosion of Zircaloy-2 and other possible reactor construction materials in UO2SO4 solutions under various conditions of radiation intensities, temperatures, solution compositions, and velocity flow past specimens.

Abstract. By means of the pulse radiolysis technique a short-lived transient species has been observed in irradiated de-aerated ethanol and methanol, exhibiting an optical absorption throughout the visible and near infra-red. This transient is suggested to be the solvated electron on the basis of the nature of the spectrum, the reactivity with hydrogen ion and with various organic electron acceptors, and the formation of mononegative ions of some of these acceptors. The absolute rate constants have been determined for the reactions of the solvated electron with hydrogen ion, oxygen and benzyl chloride in ethanol and methanol. The diphenylide ion was found to be short-lived in ethanol. The absolute rate constant for the first-order decay of the diphenylide ion has been determined.

This is a summary report of various technical projects relating to uranium.

Technical report. Form Abstract : "Perchlorate is extracted from aqueous solution by n-butyronitrile as ferrous 1,10-phenanthroline perchlorate. The amount of perchlorate is calculated from spectrophotometric measurement of the absorbance of the extract. Moderate to large amounts of chloride, sulfate, or nitrate cause little or no interference. Chlorate is slightly extracted but the interference can be corrected."

Report summarizing ongoing nuclear work performed by the ORNL for the United States Army.

Technical report. From Abstract : "The stoichiometric formula of the lower chloride in the BiCl3-Bi system has been established as Bi12Cl14 (BiCl1.167) through a dingle crystal, X-ray determination of its structure. ... Previous studies of the Bi-Cl3-Bi system are re-examined in the light of the structural results."

From introduction: Volume I of the summary report contains a detailed plant description and the results of analysis of credible accidents and the associated hazards.

From introduction in Volume I: Volume II describes those programs established by the operator to assure the safe operation of the reactor.

Technical report. From Abstract : "Paramagnetic susceptibilities of samarium structure alloys in the systems La-Gd, Nd-Y, Nd-Tm, and Ce-Y were measured from 4.2 - 300°K to determine what effect the formation of this structure has on the magnetic properties of the alloys. Susceptibility maxima were observed in the Nd-Y and Nd-Tm alloys, at 34.5 and 28.5°K, respectively. Slope changes were observed in the curve of 1/x versus T for the La-Gd alloy at 155 and 130°K, and the susceptibility of this alloy remained temperature-independent from 130-7°K. A rather poorly defined region of constant susceptibility was also observed or the Ce-Y alloy, from 26-37°K. Above these transition temperatures, the alloys obeyed the Curie-Weiss law, the susceptibilities of the La-Gd and Ce-Y samples indicating the possibility of electron transfer occurring in these cases."

Abstract: Distribution coefficients have been measured for the partition of metal ions between cation exchange resin and acetone-water-hydrochloric acid solutions. the differences in distribution coefficients of metal ions are greater in acetone-water media than in aqueous media of the same hydrochloric acid concentration. Using distribution coefficient data, conditions for column separations of mixtures can be selected. Column separations of metal ion mixtures can be effected by eluting with acetone-water-hydrochloric acid solutions of different compositions. Successful separations of a number of mixtures are reported.

Abstract: "Theoretical equations have been derived for calculating heat transfer coefficients for fluids flowing through concentric annuli for the following two cases: (A) constant and equal heat fluxes from both walls, and (B) constant, but unequal, heat fluxes from the walls, with equal wall temperatures at a given axial position along annular channel. In the derivations, the conditions of fully-established flow, and independence of physical properties with temperature variation across the flow channel, were assumed. The only geometrical parameter in this general case is the radius ratio r2/r1, and in the study it was varied from 1.0 to 10.0."

Report describing a method for planning shutdown projects and scheduling the manpower to shut down Materials Testing Reactors (MTR) and Engineering Test Reactors (ETR).

Report regarding the ongoing research and development related to the Army Gas-Cooled Reactor Systems Program. Includes status and progress of the program's projects, experiments, and data evaluations.

Summary: The following narrative interspersed with figures and attached reference exhibits is designed to acquaint the reader with the scheduling procedure developed at ORGDP, trial results and evaluation, subsequent improvement, further application, and use in conjunction with our IBM 7090 Computer.

This program was established to develop new information concerning the mechanism of diffusion of fission gases (krypton and xenon) through UO2 and UC. The work was to concentrated on measurements of diffusion rates in unirradiated materials in the temperature range of 1000°C to above 2000°C, these determinations being important to the projected use of refractory fuel materials in high-temperature, high-burnup reactors.

From introduction: This report discusses AEC-sponsored nuclear superheat meetings whose primary purpose is to keep the AEC contractors engaged in nuclear superheat projects abreast of the overall AEC superheat program and to provide a means for the exchange of current technical information.

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.

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.