105-KE downcomer pressure data are tabulated.

A survey was made of unclassified literature dealing with the control of activity build-up in pressurized water reactors by high-pH coolants. Survey results indicate that a high-pH coolant is desirable for control of induced radioactivity build-up in pressurized water reactors containing significant amounts of stainless steel and that no significant hazards are introduced by adoption of a high-pH coolant. Lithium hydroxide was found to be the most acceptable agent for coolant pH control. Strong-base-form mixed-bed resin is effective in maintaining both coolant pH and coolant purity. (auth)

Information is presented on a suitable amine processing system for plutonium nitrate. Experiments with concentrated plutonium nitrate solutions show that trilaurylamine (TLA) - xylene solvent systems did not form a second organic phase. Experiments are also reported with tri-noctylamine (TnOA)-xylene and TLA-Amsco - octyl alcohol. Two organic phases appear in both these systems at high plutonium nitrate concentrations. Data are tabulated from loading and stripping experiments. (J.R.D.)

The analysis of a reactor model that is thermally nonlinear is presented. The significant sources of feadback in the closed-loop model ane dilatational changes of the fuel due to axial expansion caused by temperature and metallurgical phase changes. Ths dynamics of this phenomenon has been represented on the Pace electronic analog com puter. The model was subjected to unusually large inputs of sinusoidal power and did not show any drastic tendencies toward being unstable. (auth)

This study is part of an evaluation of the P&W NJ- 18A powerplant. The work presented here specifically estimates the pressure drop between the compressor discharge and the turbine inlet. Analysis was asked for two operating conditions. One was for sea level sprint at a Mach no. of 0.9, while the other was for a Mach no. of 0.9 at 35000 ft.

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A critical experiment program is carried out in a configuration similar to the BONUS reactor. The results give information concerning: the effects of different boilersuperheater geometries; the reactivity changes associated with superheater voiding or flooding; power regulation between the boiler and superheater regions; epithermal transmission probabilities for B-stainless steel and Cd control rods; the power flattening characteristics; and void simulation properties. The calculational methods used in the study predict the measured reactivity and power distribution to within the limits of experimental accuracy. (T.F.H.)

This compilation was prepared to provide a comprehensive unified summary of the principal elements of the design, operation and nuclear characteristics of the Argonaut Reactor. Its primary content is made up of the theoretical and experimental evaluations of basic reactor parameters, both static and kinetic, which have been made to this date. The Databook includes also some practical information on the reaativity worths of fuel, moderator, and absorbers, as well as some data on radiation in the reactor vicinity. A list of Argonaut type reactors in all countries and a bibliography of Argonaut work are included. (auth)

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B-Plant is currently being evaluated for use as an integrated fission product plant operating in conjunction with the Purex Plant and a waste calcination system. If the forecasted demands for fission products should increase to rates exceeding present capabilities and if private enterprise continues to remain outside the recovery field, present budget plans are to develop the use of B-Plant in three phases. In Phase 1, the B-Plant canyon would be activated and provisions made for preparing and storing fission product concentrates. In Phase 2, additional equipment would be installed to provide a single-line demonstration system for purifying and packaging fission products. In Phase 3, the plant would be converted to a double-line production system for recovering, segregating and storing, purifying and packaging fission products. The purpose of this document is to present the technical bases for B-Plant project scoping studies, including: Design flowsheets for the preparation and storage of fission product concentrates in the scope design of Phase 1 activities; and conceptual flowsheets for the purification of stored concentrates in the engineering studies of Phase 2 activities.

The Birch Plant Improvement Program is described in this document. This program was instituted to fully support the AEC program for maximum recovery of neptunium from current separations feed material and other sources as the AEC may consider appropriate to their needs for increasing the availability of neptunium.

BRIC is a two-dimensional nuclear-thermal depletion program to study the effects of moderator boiling on the neutron flux distribution and the depletion of the timedependent isotopes. The program requires an IBM-704 with a memory of 32,768 words and ten tape units. (auth)

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A monte Carlo method of solving the one-dimensional equations of nonlinear radiation transport is compared with the Sn "characteristics" method of solution. It is concluded that the Monte Carlo method is accurate and stable and furthermore for a given time-cycle length and space-zone size the Monte Carlo method is more accurate than the Sn method.

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The amounts and kinds of radioactivities produced by detonation of a nuclear explosive are dependent upon the specific design of the explosive. The two design extremes are a pure fission device, which will produce about 1.4 x 10/ sup 23/ fissions, and therefore about 2.8 x 10/sup 23/ fission products, per kiloton of energy released, and a pure thermonuclear device which would produce no fission products, but would produce approximately 10/sup 23/ atoms of tritium per kiloton. In both cases, interaction of escaping neutrons with the materials of the device itself, and with the surrounding media, could lead to further radioactivities. The behavior and ultimate fate of the activities produced by the explosion depend on the composition of the medium in which the detonation occurs, the nature of the detonation, and the chemical species involved. Some typical cases are described. (auth)

An investigation was conducted to flush the 1BD coolant purification system demineralizer of resin and to measurc the radiation level at pornts on the resin discharge line. It was found that the system demineralizer was satisfactorily flushed of resin. It was also found that the amount removed is measured by the amount required to recharge the demineralizer. (J.R.D.)

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This report addresses a monthly progress report for the Chemical Technology Division for Chemical Development Section B during June 1959.

Nitrosyl and fluoride ions are formed in liquid anhydrous hydrogen fluoride when nitric oxide, nitrogen sesquioxide, nitrogen tetroxide, or nitrosyl fluoride, are dissolved. Vapor infrared analysis was used to study the solution composition and gaseous reaction products. These solutions react with metallic uranium, plutonium, zirconium, iron, and aluminum, as well as ceramic uranium oxide and uranium carbide, forming soluble nitrosyl metal fluoride complexes and liberating nitric oxide. The uranium compound identified as nitrosylium hexafluorouranate, NOUF/sub 6/, was made volatile by passing nitrosyl fluoride gas over the dry salt at 500 deg C. (auth)

Selected physical and biological data bearing upon the environmental variations created by nuclear explosions are presented in simplified form. Emphasis is placed upon the ``early`` consequences of exposure to blast, thermal radiation, and ionizing radiation to elucidate the comparative ranges of the major effects as they vary with explosive yield and as they contribute to the total hazard to man. A section containing brief definitions of the terminology employed is followed by a section that utilizes text and tabular material to set forth events that follow nuclear explosions and the varied responses of exposed physical and biological materials. Finally, selected quantitative weapons-effects data in graphic and tabular form are presented over a wide range of explosive yields to show the relative distances from Ground Zero affected by significant levels of blast overpressures, thermal fluxes, and initial and residual penetrating ionizing radiations. However, only the ``early`` rather than the ``late`` effects of the latter are considered.

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Tests were conducted to obtain data on the dynamic response of the Reactor Plant to various startup rod withdrawal transients. Results were compared with those obtained in simulator studies. (auth)