The phenomenon of the electromagnetic pinch effect is used to accelerate ionized gases for space propulsion. Electrical energy, initially stored in capacitors, is discharged across two nozzle shaped electrodes wherein the radial pinch is converted to axial motion of the effected gases instead of confinement at the axis. The gas dynamics of a pinch using the hydrodynamical model of a msgnetic piston driving a shock wave is combined with the electrodynamics of the circuit to calculate the discharge behavior. Experiments on three different electrode designs are discussed and results compared with calculated values. Results are applied to one particular space propulsion system consisting of a nuclear energy source, a space radiator, a turbine-generator, capacitor, and a pinch tube. The specific mission analyzed is a one-way unmanned flight to a Mars orbit, starting from an Earth orbit. (auth)

The performance of the Hallam Nuclear Power Facility heat transfer components was investigated in order to determine the steady-state, part load characteristics under various operating conditions. The complete steady-state temperature distributions, variations of flow rates and heat transfer coefficients throughout the sodium heat transfer systems as functions of reactor load are shown in a series of graphs. (M.C.G.)

The solubility of aluminum corrosion product in contact with metallic aluminum in deionized water has been determined over the range 80 to 350/sup 0/C. Evidence is presented to show that oxide dissolution results in the formation of a porous oxide on aluminum exposed in refreshed dynamic systems. Dynamic corrosion rate data have been analyzed on the basis of parabolic film growth and a linear oxide degradation process acting simultaneously on the system. The degradation process has been shown to be a function of refreshment rate.

In the separation of mixtures of radioactive iron and cobalt from neutron irradiated targets and in the removal of iron from cobalt targets for cyclotron production of radioiron, it is desirable to have a method superior to extraction from isopropyl ether in efficiency and ease of manipulation. Recent studies by Moore and Kraus on the separation of cobalt and nickel and on the behavior of iron in hydrochloric acid on Dowex-l resin in relation to the selective adsorption of chloride complexes of these elements have suggested the use of resin for the separation of iron and cobalt.

The relative stopping powers for 300 Mev protons of H, Li, Be, C, Al, Fe, Cu, Ag, Sn, W, Pb, and U have been measured. The results are shown in Table I. The energy spent per ion-pair production in the gases H{sub 2}, He, N{sub 2}, O{sub 2}, and A at 340 Mev proton energy has also been measured. The results are shown in Table II.

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A desirable radio-iodine emission goal for all HAPO has recently been set at one curie per day maximum. At the same time it was suggested that a more relaxed limit of ten curries per week with no more than three in any one day, would probably be satisfactory. To assure the achievement of these goal figures in the separations plants it was deemed necessary to either cool'' the irradiated material a greater length of time than is presently done before processing, or provide more efficient, iodine retention facilities. Increased power levels, higher production rates, and an increase in the awareness of radio-iodine emissions, have all coupled together to make present facilities generally inadequate when processing material aged less than about 100 days. Several alternate methods of providing additional iodine retention facilities for Redox were preliminarily scoped and presented for consideration. The purpose of this report is to present a scope design for improving iodine emission control at Redox.

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The objective of this test is to establish that scavenging of first-cycle wastes in the Bismuth Phosphate Plant will give a supernatant liquor, after the precipitate settles, that may be routinely cribbed. This test will also perform the functions: establish an effective scavenging procedure, shakedown the pH monitor, and train operational personnel. This document discusses test procedures and results.

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This document summarizes the amounts of radioactive contamination discharged to the ground from separation facilities through June 1956. Detailed data for individual disposal sites is presented on a month to month basis for the period July 1955 through June 1956. The major disposal sites in separation facilities, total volume of waste discharged at each location, and the gross amounts of plutonium and fission products discharged to the ground since startup are listed. This same data are presented on a month to month basis and also include information on the source of the waste stream and the settling facility used. Isotopic data are included for all disposal sites from which the waste was analyzed for specific contaminants. Estimates of contamination and volumes discharged to the swamps are also included.

An examination of the process scheme for handling present and future 231 Building supernatant solutions is necessary to forecast the effects of placing one of the processing facilities (224B) in a standby status and to ascertain if rescheduling of any of the supernatant solutions to 202S will be necessary. The examination indicates the 231 Building process supernates and cell cleanouts together with the 221, 224T Buildings acid washes and the 234-5 Building returns can be processed through the 224 T Building as additions to regular runs or master recycle runs when T Plant is processing as much as 41.6 tons/month of 600 MWD/T material and S Plant is processing 120 tons/month of similar material. The processing rate through, 224 T Building to satisfy these conditions is seventy-six runs per month. This total is divided into 63 regular runs plus 13 meter master recycle runs. The number of master recycle runs are primarily dependent upon the T Plant rate in as much as only one master recycle is directly required for each 35 tons processed through S Plant.

This report describes the direct essential material requirements for processing a standard run through the precipitation separations process in effect on August 1, 1954. Flow sheet conditions are based on a starting maximum batch size of 300 grams of product at a uranium irradiation level of 215 MWD/ton. The essential material requirements are those used to process with 2.5 grams of Bismuth per liter in Extraction, First Decontamination Cycle volumes at 56% of the September 1, 1946 standard, and Second Decontamination Cycle through the Lanthanum Fluoride Product Precipitation volumes at 49% of this standard.

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Studies in the 321 Building dissolver during December 1953 and January 1954, were successful in developing a laboratory-proved mercury-catalyzed dissolving flowsheet into a suitable plant procedure. However, this flowsheet was not adapted for Redox plant operation because of uncertainty about the possible presence of hydrogen above the lower explosive limit in the off-gases. Subsequent laboratory work has resulted in a better understanding of the hydrogen evolution, and has resulted in developing low hydrogen evolution flowsheets. When one of these flowsheets is selected for further work, it will be tested in the 321 Building dissolver with non-irradiated slugs to provide information for scaling-up the single-slug laboratory data to a plant-scale operation. It is the purpose of this memorandum to outline the factors considered to be pertinent to the 321 Building investigation, to be used as a guide in making preparations for the runs to be performed.

Tube 1794-C was removed from the pile as a leaker on July 15, 1954. The tube had been in-pile since startup and had contained a charge of 32 ``C`` metal slugs just prior to discharge. The tube was slit and examined at the 105-DR underwater viewing facility by Pile Coolant Studies tube examination personnel. A report is made of the examination of tube 1794-C which revealed areas of severe pitting damage. This damage was apparently caused by cocked slugs abrading the tube. The attack was great enough to cause perforation of the tube at about 27 feet from the rear Van Stone flange. Examination of the slugs showed that a considerable number had been cocked. Evidence of severe tube scarring and rib grooves was found on the slugs. Strikingly similar examples of pitting and grooving were observed on flow laboratory minitubes and slugs exposed in high velocity water. It is concluded that the damage observed both in- and ex- pile was caused by the chattering of misaligned low density slugs in a high velocity stream. If the number of in-pile occurrences of this attack becomes excessive it is recommended that the water flow rate in tubes containing ``C`` metal slugs …

Progress is reported by the Mechanical Development group and by the Plant Assistance group. The Mechanical Development group reports on the thimble removal program, special pile measurements and instruments, graphite sampling, and the ruptured slug problem. The Plant Assistance group reports on technical information on the B, D, F, and H piles, special request container slug, exposure of P-10 fuel slugs, slug corrosion studies, front tube corrosion, and flow laboratory experiments.

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The loss of cooling water from a Hanford production reactor has serious implications because of the accompanying reactivity transient. It is imperative that the time dependence of this transient be determined in order to evaluate properly some aspects of reactor safety. A previous experiment has been done however it was primarily in the nature of an exploratory run leading to the present experiment. The experiments described below cover a much wider range of conditions and have been used as a basis for analog computations to determine the adequacy of the present safety systems from a response standpoint.

This document details activities of the irradiation processing department during the month of July, 1958. 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.

This document discusses a meeting held to inform members of the Biology Division of the status of P-10 problems, to exchange ideas on methods of attacking these problems, and to consider new problems.

Recent successes with the use of metal ferrocynanides, particularly nickel ferrocyanide, for the removal of cesium from Uranium Recovery Process wastes prompted an investigation into the use of this carrier for the removal of cesium from wastes produced in the coating-removal and first-decontamination-cycle steps of the Bismuth Phosphate Process. Both in-line treatment of the wastes currently produced and treatment of supernatant liquids from wastes already stored in underground tanks were considered.