This annual report of Brookhaven National Laboratory describes its program and activities for the fiscal year 1958. The progress and trends of the research program are presented along with a description of the operational, service, and administrative activities of the Laboratory. The scientific and technical details of the many research and development activities are covered more fully in scientific and technical periodicals and in the quarterly scientific progress reports and other scientiflc reports of the Laboratory. A list of all publications for July 1, 1957 to June 30, 1958, is given. Status and progress are given in fields of physics, accelerator development, instrumentation, applied mathematics, chemistry, nuclear engineering, biology, and medical research. (For preceding period see BNL-462.) (W.D.M.)

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A description of the Argonne 60-in. cyclotron along with its performance, operstional characteristics, and housimig with its associated facilities is presented. (J.E.D.)

Dogs, pigs, rabbits, guinea pigs, and mice were exposed to nuclear detonatiors in two open underground pantitioned shelters. The shelters were of similar constructions and each was exposed to separate detonations. Each inner chamber filled through its own orifice; thus four separate pressure enviromments were obtained. An aerodynamic mound was placed over the escape hatch of each structure to determine its effect on the pressurecurve shape inside the chamber. In one test a sieve plate bolted across the top of the mound was evaluated. Wind protective baffles of solid plate and of heavy wire screen were installed in the shelters to compare primary and tertiary blast effects on dogs. The shelters also contained static and dynamic pressure gages, radiation detectors, telemetering devices, and, in one test, air-temperature measuring instruments, dustcollecting trays, and eight pigs for the biological assessment of thermal effects. One dog was severely injured from tertiary blast effects associated with a maximal dynamic pressure (Q) of 10.5 psi, and one was undamaged with a maximal Q of 2 psi. Primary blast effects resulting from peak overpressures of 30.3, 25.5, 9.5. and 4.1 psi were minimal. The mortality was 19 per cent of the mice exposed to a peak …

Dogs, pigs, rabbits, guinea pigs, and mice were exposed to nuclear detonations in two open underground partitioned shelters. The shelters were of similar construction, and each was exposed to separate detonations. Each inner chamber filled through its own orifice; thus four separate pressure environments were obtained. An aerodynamic mound was placed over the escape hatch of each structure to determine its effect on the pressure-curve shape inside the chamber. In one test a sieve plate bolted across the top of the mound was evaluated. Wind protective baffles of solid plate and of heavy wire screen were installed in the shelters to compare primary and tertiary blast effects on dogs. The shelters also contained static and dynamic pressure gages, radiation detectors, telemetering devices, and, in one test, air-temperature measuring instruments, dust-collecting trays, and eight pigs for the biological assessment of thermal effects. One dog was severely injured from tertiary blast effects associated with a maximal dynamic pressure (Q) of 10.5 psi, and one was undamaged with a maximal Q of 2 psi. Primary blast effects resulting from peak overpressures of 30.3, 25.5, 9.5, and 4.1 psi were minimal. The mortality was 19% of the mice exposed to a peak pressure of …

Report issued by the Brookhaven National Laboratory discussing the work conducted by the lab during the fiscal year of 1958. As stated in the introduction, "the progress and trends of the research program are presented along with a description of the operational, service, and administrative activities of the Laboratory" (p. vii). This report includes tables, illustrations, and photographs.

A study to define the effectiveness limits of sulfamic acid and to discover other better stabilizers for Pu(III) is described. Ascorbic and isoascorbic acids, used in conjunction with sulfamic acid reduced Pu(IV) to stable Pu(III) in nitric acid. Aminoguanidine sulfate also retarded the oxidation of Pu(III) but did not reduce Pu(IV). (J.R.D.)

Technical report. From Abstract : "Ascorbic and isoascorbic acids, used in conjunction with sulfamic acid, reduced Pu(IV) rapidly and completely to Pu(III) in solutions of nitric acid. The solutions of Pu(III) were stable. Aminoguanidine sulfate also retarded the oxidation of Pu(III) but did not reduce Pu(IV)."

(((Abstract unscannable)))<><DSN>13:014503<ABS>Thc Nb-O equilibrium system was determined by metallographic examination of arc-cast alloys made ot electron-gun-refined Nb metal and special purity Nb/sub 2/O/sub 5/. Two intermediate oxides. NbO and NbO/sub 2/, melt without decomposition at 1945 C and 1915 C, respectively. Eutectic reactions exist between Nb and NbO at 1915 C and between NbO and NbO/sub 2/ at 1810 C . Experimental evidence supports a peritectic reaction between NbO/sub 2/ and Nb/sub 2/O/sub 5/ at 1510 C. The maxinium solid solubility of 0 in Nb metal is 0.72 wt.%. (auth)

BS>Critical concentration calculations were made for several D/sub 2/O-H/ sub 2/O moderated HRT-type reactors with 30- and 28-in. core diameters and pressure vessel diameters of 60 and 54 in. A core temperature of 300 C was assumed for all cases while the blanket temperatures assumed the values 250, 280, and 300 C. The assumed moderator compositions were 80, 90, and 100% D/sub 2/O. (auth)

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.

Design analysis of a prepackaged nuclear power plant.

Design analysis of a prepackaged nuclear power plant.

ABS>Published information is not available for accurate prediction of the electrical insulating characteristics of helium at high pressures and temperatures. In general the breakdown voltage increases as the gas pressure is increased and decreases as the gas temperature is increased. The relatively low breackdown voltage of helium accents the importance of additional investigation in this field. (auth)

From introduction: This report is a summary of the detailed geologic and engineering information that is available on three sites for underground explosions on the Nevada Test Site.

From abstract: The Fluidized Bed Reactor (FBR) consists of a bed of fuel pellets which circulate in a confined core region as the result of the upward flow of fluid through the particles. In the present concept the fluid acts as a fluidizing, coolant and reactor moderator medium. This report is the results of the Phase I study to determine the feasibility of this concept.

A laboratory study of a gelatin headend process for feed from silicon- containing aluminum fuels and plant salvage solutions is described. The optimum conditions for the gelatin treatment of fuel solutions were to boil a 0.1 to 0.5N nitric acid solution with 100 milligrams of gelatin per liter for 30 minutes. This treatment improved filtration rates and decreased the surface activity of the filtrate for TBP extraction. A number of possible flowsheets for fuel solutions are presented using gelatin treatment and filtration. An adequate treatment was not found for salvage solutions of unknown composition because a gelatin dosage which was satisfactory for all solutions could not be selected. The optimum treatment for a salvage solution which was grossly contaminated with zirconium, soluble and colloidal silica, and dibutyl phosphate was to boil a 1N acid deficient solution with 600 milligrams of gelatin per liter, filter, and use a Hexone extraction system. A silicic colloid in fuel processing solutions was characterized as a surface active material by this study. (auth)

From introduction: The papers comprising the various parts of this report contain the preliminary results of the U. S. Geological Survey investigations in the Ul2e.05 tunnel at the Atomic Energy Commission's Nevada Test Site, Nye County, Nevada (fig. 1). Reports on electrical resistivity, natural radioactivity, and heat required to raise the rocks to 100C will be issued later. A preliminary report on the geologic effects of the Blanca event is being prepared.

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This document details activities of the Hanford Operations Office during the month of February 1959. (FI)

Report concerning the "determination of the validity of using tube flow correlations for calculating pressure drop and heat transfer characteristics in thin annuli," the "validity of using Stein's heat flux asymmetry correction for parallel planes to calculate the heat transfer in asymmetrically heated thin annuli," and the "investigation of the effects of eccentricity on pressure drop, heat transfer, and temperature distribution in concentric ring fuel elements" (p. 5).

The fixation of aqueous radioactive wastes in a stable solid media by means of calcination has been the subject of considerable research and development effort. Several methods of doing this on a continuous basis have been devised and a few have been demonstrated to be feasible for the handling of non-radioactive or low activity simulated wastes. Currently an investigation of calcination by means of radiant-heat spray drying is being carried on by the Chemical Research Operation of the Hanford Laboratories Operation. The process consists of atomizing the liquid to be treated into the top of a cylindrical column, the walls of which are maintained at a high temperature. The resultant suspension of droplets in the water vapor formed by evaporation passes through successive zones of drying, calcination, possible chemical reaction or melting, and partial cooling as it proceeds down the tower. Separation of the resultant solids, steams, and uncondensable gas is made by conventional methods.

Information concerning graphite contraction applicable to high- temperature, graphite-moderatored reactors is presented. The scope includes relevant data from all available sources, interpretation and extrapolations as can reasonably be made, and a discussion of the effects observed in terms of current radiation damage theory. Limits of accuracy and a discussion of experimental techniques are presented. (auth)