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.

Up to one hundred ribless zirconium process tubes are to be installed in C Reactor, and necessary reactor equipment modifications made to permit routine charging of these tubes with self-supported natural uranium fuel elements. This test authorizes continued loading in these tubes until authorized by process standards or until it is deemed impractical to convert C Reactor to this geometry.

Six 1.6% enriched Zircaloy-2 jacketed seven-rod cluster elements with modified end supports and one Zircaloy-2 jacketed Pu-A1 seven-rod cluster element will be irradiated in KER Loop 1 to an exposure of about 4500 MWD/T.

Objective of this test is to authorize irradiation of alloyed, low hydrogen dingot uranium fuel elements on a pilot scale, and to monitor their performance. Initially, 25 tons per month of alloyed, low hydrogen dingot material will be charged for two months. Measured charges will be loaded with the initial 25 tons to monitor the stability of this material. Following a two-month delay in the monitor charging, and if the dingot meets all specifications, routine charging of quantities up to 60 tons/ month may proceed for six months and, assuming continued favorable performance, up to 150 tons/month may be accepted to complete large scale evaluation of dingot uranium, and on a continuing basis thereafter.

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Pu production from separation plants was only 65% of the monthly commitment owing to Purex difficulties. UO{sub 3} production and shipments both met schedules. Although unfabricated Pu metal production was reduced, all shipping commitments were met on schedule. Purex equipment responded satisfactorily to decontamination. 860,000 Ci of Ce{sup 144} were recovered from Purex Conc. IWW. The all-Ti L-3 concentrator loop was installed in the Redox Pu Concentrator. The safety of the slag and crucible dissolver in Finished Products Operation was improved by adding cadmium to each batch. Engineering studies of Palmolive facilities are reported. An emergency water supply for the Purex 241-A waste storage tank farm will be installed. A study was made on casks for NPR fuel shipment. (DLC)

This report gives results of a study of the effect of changes in axial power distribution on rupture potential. Possible interrelationships between this effect and the effects of other reactor variables were investigated.

This document details activities of the Fuels Preparation Department during the month of July 1959. (FI)

To evaluate the self-supported fuel element concept, tests are underway to determine the performance of collapsible bridge-rail supported fuel elements in ribless process tubes under present reactor conditions at B Reactor. It appears expedient, however, to extend this evaluation to future operating conditions in order to establish the relative feasibility of conversion to self-supported fuel elements in ribless tubes in present reactors. Utilization of 1.47% U-235 enrichment will provide fuel element powers comparable to those attainable under proposed future conditions. Since I & E fuel elements of this enrichment have previously attained exposures in excess of 2000 MWD/T at specific powers averaging 75 KW/ft in C Reactor, this test will specifically evaluate the feasibility of the self-supported fuel element concept. The purpose of this report is to present the design of a test to fabricate and evaluate self-supported fuel elements under conditions of comparable severity to those expected for future loadings of this geometry.

This document details activities of the irradiation processing department during the month of July 1959. 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; facilities engineering operation; employee relations operation; and financial operation.

The air quench prior to water quench during core heat treatment can be used to control slug distortion. In August 1959, a production test authorized the charging of 16 tubes of 43-second air quench material alternated with standard control material in C-Reactor. The test was charged on November 24, 1958, and discharged on April 26, 1959. This report summarizes and evaluates the irradiation performance of the material.

The object of this production test is to authorize the irradiation of samples of natural uranium for use in the fission product volatilization program. Any empty central zone PCCF and/or process tube at B, D, DR, or H Reactors will meet the requirements of this authorization.

The following criteria outlines the basis, objectives, and fundamental methods that shall govern the preparation of final design for ``Project CGI-839, Modification to Fuel Element Test Facilities -- 1706 KER.`` These modifications will provide the equipment to test NPR size fuel elements in the KER recirculating loops. The 1706-KER Recirculation Test Facility of KE Reactor is operated to obtain experimental data regarding high temperature reactor coolant technology and high temperature fuel element testing. The facility consists of four in-pile recirculating loops. These loops will permit testing of fuel elements with the existing process tubes of 2.1 inches I.D. To provide adequate in-reactor fuel element test facilities to support the development of NPR fuel, two KER loops, {number_sign}3 and {number_sign}4 will be converted to provide a process tube of 2.7 inches ID that will be operated at typical NPR irradiation conditions. The remaining loops No. 1 and 2, will be modified to provide additional flow and heat transfer capacity for greater flexibility in the testing of high temperature fuel elements smaller than the NPR size. New pumps, heat exchangers, and minor piping modifications will be required in all loops.

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A resume of Health Physics activities for April, May, and June, 1959 is presented. Discussions and tabulations which summarize results of field surveys, biooassy, personnel monitoring, and environmental surveys are included. The thorium redrumming program reactivated for the summer. Work is in progress to move th "HH" Building process to the "T" Building. The ventilation system for the Hot Gas Facility was extended to handle the ventilation requirements for tthe R-108 Surveillance facility. "Hot" work in R-108 began in June. During this quarter "hot" work was initiated in the new Plutonium Alloy Research facility. Health Physics design criteria for the proposed Clover facility has been submitted to the Engineeering Department. The installation of the air monitoring systems in the new Cryogenics facility and iin the new Ceramics facility is essentially complete. We have embarked on the program of converting all of our personnel monitoring and survey record keeping systems to the IBM system.

Results of an analysis to determine the extent of displacement of the EGCR core due to blowdown in case of several postulated hot main gas coolant pipe failures are summarized. Results show that the core will be damaged for ary hot pipe double-ended failure. Excepting the improbable case of no coolant flow existing prior to the break, the core will be damaged for any hot pipe fracture exposing a total flow area to the atmosphere equal to that of one pipe. Smaller breaks will probably be safe in this respect. (auth)

A tabulation (too large to be included in the memorandum) of the hypergeometric probability distribution for lot sizes up to and including 50 is described. Uses of the tabulation in sampling inspection and reliability are described. The tabulation provides a simple way of testing the equality of two proportions when the total number of observations on the proportions does not exceed 50. (auth)

The development of bakeable high-vacuum flanges for the ORNL PIG Facility is reported. The general design approach for this type flange is to obtain a bakeable vacuum seal by first welding thin metal rings to a set of heavy metal flanges, and then edge-welding the rings together. This design sllows the option of O-ring sealing for nonbaked operation. A number of flange designs are discussed together with fabrication inspection, testing, and installation and maintenance information. (auth)

The advantages of storing nuclear pulse height information on tape for later use with an analyzer are pointed out. Experiments with a magnetic modulator playback head which would offset inaccuracies due to tape speed variation are described. (T.R.H.)

Efficiency of the pilot plant pumper-decanters was greatly improved by the maintenance of interfaccs. The low efficiency of the D-3 pumper-decanter in the plant could be substantially raised by an interface to prevent backmixing. A review of refinery performance, based on a correlation of wash raffinate density with extract uranium saturation showed that high-thorium product resulted from low extract saturation. Tributyl phosphate recovery by hexane stripping of raffinate can be greatly improved through the use of a pamper-decanter in place of the present open column. The pilot plant fluid-bed denitrator has been operated at production rates as high as 500 lb UO/sub 3/hr-sq ft using hlgh feed concentrations. Correlations of previous particle size and heat transfer data are presented. A pilot plant fluid-bed reduction reactor with a tapered internal mandrel has been placed in service. The equipment has performed well in preliminary runs. Equipment to convent low concentration to 38% HF by distillation has been installed. Runs have been made in the green salt reactors in order to simulate the conditions whereby the 38% HF will be utilized. These runs demonstrate the ability to produce high-quality UF/sub 4/ utilizing 38% HF to the Air reactor tube. Laboratory analysis of green …

The effects of simulated space vehicle vibration, acceleration and shock on the operation and efficiency of a SNAP-III thermoelectric generator are described. The test specifications were developed by Jet Propulsion Laboratories for the third stage and payload of the Vega Vehicle. (auth)

A progam to determine the effect of variations of Al content, heat treatment, and basic slip mechanism upon room temperature ductility of Fe--Al alloys is reported. (W.L.H.)