Memorandum presenting various reports regarding the use of hydrogen for turbojet and ramjet powered flight. Some of the characteristics considered include the combustion properties, potential fueling problems, and flight experience with hydrogen on-board.

Memorandum presenting an investigation to determine the performance of the J65-B-3 turbojet engine with JP-4 and gaseous-hydrogen fuels. With JP-4 fuel, the maximum altitude for stable combustion was from about 60,000 to 65,000 feet, and the ultimate blowout limit was at an altitude of about 75,000 feet. The steady-state performance with either fuel decreased considerably with increasing altitude.

Report discussing the personal aspects involved in the research on transcurium elements at the Lawrence Radiation Laboratory, as well as a brief summary of previously unpublished work with heavy ions.

Report discussing a study regarding the time-dependent neutron flux for a pulsed subcritical assembly. From abstract: "A two-group analysis has been applied to the transient behavior of the thermal flux in a subcritical assembly which has been given a short burst of fast neutrons."

Abstract: "Measurements have been made on pseudo-cylindrical graphite-enriched uranium unreflected systems. These measurements include both critical mass determinations and time dependent measurements using a pulsed neutron source to drive the assemblies."

"An experimental study has been made regarding the passage of a beam of 100-kV ions (H⁺ and H₂⁺) across a magnetic field by means of a crossed electric field." This experiment was designed to answer the following questions: "(1) Is there a limit to the current that will traverse a magnetic field by the action of a crossed electric field? If so, what is the limit? (2) Do difficulties arise in maintaining the electric field? (3) For the source employed, what is the angular divergence and current density of the beam?"

From abstract: This bibliography consists of references pertaining to "Effects of Nuclear Radiation Upon Electronic and Electrical Components", and to "Electronic and Electrical Components for Critical Environments". References were compiled from the Classified and Unclassified report literature and the published literature. The following indexes and abstract journals were used: Weapons Data Index, AEC Card Catalog, Engineering Index (1950-55), and Office of Technical Services, Research Reports (1956-March '57).

This document details activities of the irradiation processing department during the month of March, 1957. A general summary is included at the start of the report, after which the report is divided into the following sections: Research and Engineering Operations; Production and Reactor Operations; Facilities Engineering Operation; Employee Relations Operation; and Financial Operation.

Owing to continuous uranyl nitrate calcining facilities at Hanford, the reactivity of the A oxide produced was reduced, with lower conversion to UF{sub 4}. A process design was developed for increasing the A{sub 3}O{sub 8} activity by fluidized-bed reduction to UO{sub 2} and reoxidation to A{sub 3}O{sub 8}. Justification for the installation would be in the $250,000 to $300,000 saved in not needing additional fluorine cells and $310,000 per year operating cost savings. The installation would cost $700,000 or $860,000; operating cost would be $270,000 per year. It was concluded that a full-scale process cannot be justified at the time of the study.

From acknowledgement: This report was prepared as a joint effort by the personnel of Yankee Atomic Electric Company, Westinghouse Electric Corporation, and Stone & Webster Engineering Corporation for the purpose of preparing an operating license application.

The results of two-dimensional (r,z) multigroup calculations of an experimental low-power reactor (PPA19) are described. Comparison is made between calculated results and experimental measurements of reactivity, power distribution, and sodium activation. Generally good agreement is observed between calculation and experiment. This calculation was performed in 1954 and represents the first application of Roe's twodimensional multigroup formulation to the analysis of an operating critical assembly. The over-all objective of such calculations is to ascertain the accuracy of two-dimensional multigroup methods in order to facilitate their application to future problems in reactor design. (auth)

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Summary: The scope and intent of this report is to demonstrate the feasibility of a nuclear powered tanker for service in the United States Maritime Fleet.

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Flowsheets are presented for the solvent extraction recovery of uranium and Np/sup 237/ from special highly irradiated MTR fuel elements and from nonvolatile fluoride residues from the Oak Ridge Gaseous Diffusion Plant. In both cases the material containing the neptunium and uranium is dissolved and digested to inactivate emulsion-forming impurities, the neptunium and uranium are extracted with tributyl phosphate solvent, using aluminum nitrate as the primary salting agent, scrubbed free of fission products and/or ionic contaminants, and finally separated and recovered by selective stripping with nitric acid. (auth)

The proposed Yankee Atomic Electric Company Reactor is a pressurized light water reactor plant designed to produce ultimate1y 492 Mw of heat and 134 Mw of net electrical generation at full power. The initial core to be operated in the reactor is designed to produce 392 Mw of heat at full power which provides approximately 110 Mw of net electrical generation. The reactor is fueled with slightly enriched uranium dioxide UO/sub 2/, in the form of pressed and sintered 0.3 in. diameter cylindrical compacts stacked in 0.336 in. OD full length stainless steel tubes in a core 7.5 ft. in height. The reactor is cooled and moderated by light water. The design is subject to change in detail before manufacture. Design characteristics and reactor safeguard considerations are described. (C.H.)

The difference in rates of reaction of isotopic molecules may be utilized to produce appreciable isotope enrichments. When a competitive irreversible isotopic reaction is carried out to a high extent of completion, the residual unconverted substrate becomes exponentlally enriched in the heavier isotope. In deuterium systems, a substantial function of the D inventory is retained in the enriched residual substrate, so that conversion of the depleted product is unnecessary. For isotopes of heavier elements such as C/sup 13/, N/ sup 15/, and O/sup 18/ the retention is low, so that product conversion and recycling is desirable unless the starting material is of negligible value. Experiments are described in which enrichments of C/sup 13/ have been obtained using the reaction rate principle in dehydration of formic acid and hydrolysis of urea. Procedures are given for the preparation of decimolar barium carbonate at the level of 1.6% C/sup 13/, and molar barium carbonate at the 1.4% level starting with commercial materials. (J.R.D.)

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A representative selection of stainless alloys was exposed in sulfur- bearing cracked-ammonia atmospheres containing 43 vol. % water vapor. Experimentally controlled variables have included temperatures ranging from 1200 to 1800 deg F and S levels ranging from zero to 350 grains per 100 ft/sup 3/ of cracked ammonia. It has been found that high S levels do not result in any significant change in the corrosion behavior of materials evaluated. Increasing the temperature resulted in some modifications or Moth physical properties and scaling resistance; however, these changes are a function of the temperature and not an effect of S. (auth)