Report describing the determination of the absolute value of the acceleration due to gravity at the National Bureau of Standards.

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This report describes research, development, support, and test activities in the Sandia Laboratory Aerospace Nuclear Safety Program for May 1968.

The purpose of this program is to conduct studies in the freshwater environment to acquire data needed to evaluate and predict the potential radiation hazards to human populations in the defined regions of proposed nuclear excavations in the Republics of Panama and Colombia. The results of the field surveys conducted in Phase II are presented in this report. Specifically, the data describes the elemental composition of the major components of the ecosystem, and reports the calculated stable element concentration factors for the major food organisms. This data provides baseline values from which predictions can be made of the potential maximum radionuclide intake by populations using this resource.

This report is on Chronology of Congressional Interest in Geographic Distribution of Federal Research and Development Funds, 1963-1967 with Annotations 1968.

Report of the U.S. Army Engineers describing the geography of Colorado River and Tributaries Texas covering mouth of colorado River including the likelihood of floods and benefits of flood control

From introduction: "The development of one or more nuclear steam supply system concepts, with certain trade-off studies to aid in the definition of these concepts. The selection of a reference concept for further study."

The purpose of this report is to describe the work accomplished to date in developing and implementing a computer programmed mathematical model for NSS reliability analysis.

The following report describes the computer technique for tracing seismic rays in two-dimensional geological models in the state during the time this report was written, and presents some preliminary results.

The following report explains the seismic ray models presented in this report.

This report describes the correlation study of the ultrasonic shearwave inspection of nozzle coolant-channel brazed shear-joints.

Monthly newsletter of the High Plains Underground Water Conservation District No. 1, discussing the field of underground water. Topics include profiles of water conservation research, annual pre-plant soil moisture survey data, annual Winter Water Level measurement data, and information about the latest water conservation tips.

Report regarding the ninth Development Run of Saline Water Conversion Demonstration Plant Number 1. Primary objectives include studying "various aspects of heat transfer and sea water and condensate treatment and their effect on the Multiple-Effect Long-Tube-Vertical Evaporation Process" (p. 1).

This report presents the details of the activities of Douglas United Nuclear at the Hanford site during the month of May 1968.

This report deals exclusively with the necessity for Senate confirmation when an Associate Justice is elevated to the Chief Justice of the United States. The paper assumes sub silentio that Congress is in session when the appointment is made.

The efficiency of producing Pu-238 from Np-238 depends on the relative absorption cross sections of the target, Np-237, and the product, Pu-238. A lowering of the Pu-238/Np-237 cross section ratio reduces the destruction of Pu-238 formed during reactor operation. The absorption cross sections of both these isotopes are strongly neutron energy dependent; the absorption cross section of Pu-238 decreases more rapidly with thermal neutron temperature increases than the conventional v{sup {minus}1} dependency and exhibits negligible resonance absorption. On the other hand, Np-237 is a very nearly v{sup {minus}1} thermal neutron absorber and has dominant low level resonance cross sections. Thus, for higher thermal neutron temperatures and a more epithermal neutron spectrum, depletion of the Pu-238 product is reduced relative to Np-237 burnout. The relative absorption cross sections of these two isotopes were calculated for the K and N Reactors as a function of graphite temperature for two linear densitie of neptunium in the target elements for each.reactor type. The method of calculation was as follows: The HAMMER integral transport code was used to obtain region and cell averaged four-group cross sections for both the fuel and target cells. These cross sections were then used in the HFN diffusion theory code …

A primary factor in assessing the impact on the biosphere of the discharge of heated reactor effluent to the Columbia River is the degree of initial dilution. Each of the reactor effluent lines discharges at the bottom of the river, approximately normal to the current, and near the main channel. As part of the Division of Production research and development program titled ``The Effects of Reactor Effluent on the Quality of Columbia River Water,`` the temperature measurements recorded in this document were taken over a period of several years. Generally, the exact locations of the ends of the effluent lines could not be determined from the river. The intent therefore was to determine the initial degree of dilution at the point where the mixed effluent first reached the surface, the so-called ``bubble,`` over a range of river flow-rates. A secondary goal was to determine the distance downstream (in quarter-mile increments) at which vertical mixing of the effluent streams could be considered complete. The data reported here have been partially reported previously and used in the development of a mathematical model of plume development. The purpose of this document is to provide a record of the field data in more detail …

This report briefly summarizes many of the provisions of the elections laws of the fifty states and the District of Columbia.

Report investigating concrete for use in a sea water desalination plant. Concretes containing both natural and limestone aggregates were tested under the temperature, pressure, salinity, and structural stress conditions that could be expected in such a plant.

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This report covers the proposals and reactions from the Federal Data Center.

The development of a high heat flux heater for use in corrosion rate and stress-rupture tests of fuel cladding materials in a sodium environment is described.

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Report presenting of survey of the literature on the infrared spectroscopy of carbohydrates in order to assemble and systematize information in this field. Discusses principles and instrumentation, sampling techniques, comparison of samples, and the interpretation of the spectra. In addition, examples are discussed of the use of infrared spectra for qualitative and quantitative purposes and in the determination of structure. Special techniques are briefly described.