Report issued by the APDA over HAFEVER, a code developed for the IBM 704 computer. As stated in the introduction, "HAFEVER is an IBM 704 code which calculates the energy exchange inelastic scattering cross section" (p. 3). Descriptions of the code and the theory behind the code are discussed. This report includes tables.

The following report describes a mass flow system that can measure homogeneous flow, slurries, highly corrosive fluids and multiphase fluids, with the addition of considering pressure drops, measuring external to the flow, ruggedness and reliability.

Abstract: This report is a description of a 200 channel digital recording system used to record high temperature strain gage outputs and associated temperatures.

Abstract: "Discussion is directed toward eventual optimization of the largest diffusion-pump systems. Less than 100 diffusion pump fluid molecules per cm 2/sec are possible to detect using an accumulation method. Optimization discussed demands highest possible system speed compatible with the above contamination rate. Bakeable oil diffusion pump systems, with equal orifice valve-tap units, without conventional baffling, permit theoretical through-put speeds up to 0.3 of the system orifice. The average backstreaming rate of oil in two unconventionally baffled commercial pumps of 6-in. and 10-in. size is reduced to < 3 x 10-(-4) g/cm-2/24 hr, including heating and cooling the pump boiler. A Ho factor of >0.4 is maintained. Results on trapping with activated alumina, retained by a wire mesh, at both liquid-nitrogen and room temperature are included. A variety of pumping speed measurements and bakeable combination valve-trap units are discussed."

From introduction: This report is a summary of the lecture material in the training course held at Idaho Falls, Idaho, to familiarize members of radiological assistance teams with information helpful in the response to an unusual accident including release of radioactive materials to a populated environment.

Abstract: The results of this investigation leave little doubt that diffusion of the fluorinating gas along the grain boundaries of the nickel fluoride film to react at the metal-scale interface is the primary mechanism of attack upon pure nickel and its more promising alloys.

A digital comparator has been designed to flag data which goes above a maximum limit or below a minimum limit.

From introduction: The maps and tables comprising this report are being transmitted at this time to provide interested users with a summary of the geology of the Ul2e tunnel system. The system was constructed to provide access to underground test sites. This report contains part of the geologic information obtained from investigations conducted by the U. S. Geological Survey to determine the geologic environment of the underground test sites. Results of geophysical and radiometric surveys, and physical properties are being studied. This work was done on behalf of the U. S. Atomic Energy Commission.

The purpose of this report is to present all pertinent geologic data on an area in which relatively imprtant uranium deposits are present.

Discussing peaceful applications of nuclear explosions

Abstract. A series of paired explosions in a salt mine near Winnfield, Louisiana, has been conducted to test a theory by Dr. A. L. Latter concerning seismic decoupling by underground cavities. The theory predicted a decoupling of about 100. Free-field and surface measurements from an explosion in either a 6-ft- or a 15-ft-radius spherical cavity were compared with similar measurements from a completely tamped explosion. Shot sixes were from a 10 lb up to a few tons. Surface measurements were made out to 100 km and covered the frequency range from 0.05 to 100 cpa. The experiment confirmed that decoupling does occur. The actual decoupling factor as a function of frequency is presented and compared with the Latter theory.

In this paper, a theoretical solution is developed for the transient thermal stress distribution in a reactor fuel tube of circular cross sections with spatially uniform internal power generation and forced convective heat transfer at the inner surface of the tube. Solution of the equation of heat conduction is done my means of a Laplace transform with subsequent application of the inversion integral to arrive at a final expression for the transient temperature distribution. The solution is of interest in the analysis of transients in reactors which use either a gas or liquid heat transfer medium. The work was initiated in conjunction with the quench testing of ceramic fuel elements for a gas-cooled reactor. Expressions for the component stresses are given explicitly and examples of application of these formulas to startup of a gas cooled reactor and the flow quenching of a fuel tube are given.

Abstract. The waveform or character of a refraction arrival has become internationally important because of its use in determining source parameters. An approximate theoretical machine calculation has been made to show the effect of layering above a refractor on the character of the refraction arrival. The method is illustrated with a geologic model taken from the Edwards Plateau area of West Texas. The effect of the Edwards limestone, Comanche, and Trinity formations on the refraction from the Pennsylvanian limestone is computed. The conversion of energy in theses upper layers from compressional to shear plays a significant role in forming the refraction character. An anticlinal structure is introduced into the Pennsylvanian limestone and it is argued that, in a first approximation, the wave in the Pennsylvanian limestone follow the structure, refracting off at the critical angle as before. Now, however, the angle of incidence on the base of the Trinity is a function of the angle of the structure. Since the amplitudes of converted waves depends n this angle, The character of the refraction arrival depends in a predictable way on the angle in the structure where the critical refraction has taken lace. These results are theoretical and only approximate, but …

Some consequences of the existence of a neutral spin-0 particle with imaginary parity are examined. The particle is subsequently identified with K0 and it is shown that associated production is a consequence of a super-selection law for parity. The parity of the K0 is fixed by its electromagnetic interaction, which leads to certain results that differ from those predicted by strangeness. The theory accounts directly for the non-conservation of parity in non-neutrino decays of Λ, Σ's and K's.

This bibliography lists selected articles on molybdenum, niobium, tantalum, tungsten and uranium oxide in the journal literature of the U.S.S.R. The following sources were used and also are noted after each citation, Special Library Association Translation monthly 1959-June 1960, U.S. Library of Congress Monthly index of Russian accessions 1955-June 1960, U.S. Office of Technical Services Technical translations 1955-1958.

"We compute the equilibrium configuration of a collision-free plasma contained in an axially symmetric magnetic field. The plasma is characterized by a non-scalar pressure tensor which is obtained from a microscopic distribution function in a form suggested b the guiding center approximation. The solution is calculated in the limit where the ratio of the width to the length of the plasma region and the ratio of the gas to the magnetic pressure are both small. Boundary values at the midplane as well as the shape of the plasma appear as arbitrary parameters in the solution. We give the solution to a corresponding scalar pressure problem for comparison."

"In this paper we solve for the diffracted wave which results when a weak hydromegnetic shock impinges on a rigid perfectly conducting half plans."

A flexible foil data processing program is described. Raw data on foil radioactivity are the basic input information required. Output may consists of relative activities, saturated activities, and/or cadmium ratio and flux spectrum data. A statistical analysis of the data is executed with the direct calculation, and errors estimated for the output data.

"A survey is presented of the theory of confinement in open-ended systems (such as mirror machines and cusped geometries) together with the slight amount of experimental confrontation with theory that exists at present."

Conclusions from the study: "Radioactive dusts are carcinogenic, and can cause cancer of the lung. complete dose response curves have not yet been determined. All the parameters that render this demonstrably toxic material (radioactive dust) have not yet been evaluated. It is strongly suggested by the experimental data that duration of radiological insult to the lung is an important factor in eliciting lung cancer. The atmospheric tolerance concentrations now in use seem to afford little margin of safety."

From Abstract: "The data for gummed film fallout measurements through December 1959 are reported. The bulk of the report consists of summary tables for each gummed film station listing the monthly estimates of strontium 90 deposition and infinity gamma dose."

This technical report represents the final design for a sodium to sodium intermediate heat exchanger and a sodium to water steam generator. The intermediate heat exchanger is designed for operation in a nuclear power plant using liquid sodium as the primary and secondary coolant. Since the primary fluid coming fro the reactor is radioactive, the purpose of the IHX is to transfer heat to a nonradioactive fluid which then goes to the steam generator. Because of radioactivity the unit will be enclosed in a concrete pit and will not be accessible during periods of operation. Immediately after shutdown it will be necessary to allow time for radioactive decay before the unit will be accessible to personnel. Because of inaccessibility and possible long periods allowed for decay time, it is imperative that the unit give trouble free operation. During periods of shutdown, the internals should have easy access for inspection and repair if necessary so that down time is held to a minimum. The steam generator is designed to generate superheated steam using liquid sodium from the intermediate heat exchanger as the heat source. Its basic design is a shell and tube unit made up of three difference sections: (1) a …

Introduction: This volume deals principally with the chemical analysis and the stress analysis for a sodium to sodium intermediate heat exchanger and a sodium to water steam generator. The work presented is an extension and modification of the analysis presented in the preliminary design report. The chemical analysis covers the sodium cover gas system and the effects of sodium-water reactions in the event of a leak in the steam generator. Considerable design work was done in an effort to maintain the integrity of the steam generator vessel under maximum leak conditions. The method of sizing relief valves for each unit under varying leak rates is presented in this text and operation of the unit for the various leak rates is resented in the Operation and Maintenance volume. The stress analysis section covers those thermal transients which would be physically possible with this intermediate heat exchanger and steam generator design. Attention has been given to methods of operation which would minimize the magnitude and frequency of thermal shocks. Certain areas have been studied in detail where thermal stresses appear high. This report also includes a structural design basis for handling stress analysis of combined mechanical, hydrostatic and thermal stresses and conditions …

Introduction: Sodium Components Material Specifications. Twenty-three material, inspection and welding specification are presented for the various parts of both the intermediate heat exchanger and steam generator. Tables indicate the applicable parts and assemblies to which these specifications shall apply. For other parts, where the material requirements are not severe, the ASTM or other indicated specifications shall apply.