A study was made to determine whether secondary iso tope effects also occur in molecular structure. Electron diffraction studies were carried out on ethane and deuteroethane. In C/sub 2/H/sub 6/ the mean C-C and C-H bond lengths found agreed very closely with values determined for other paraffin hydrocarbons, and the C--H bond showed a normal primary isotope effect (~ 0.005 A) similar to that found in methane when H is replaced by O. The output of the leastsquares analysis suggested that the mean C-- C bond length in C/sub 2/D/sub 6/ is shorter than in C/sub 2/H/sub 6/ and by about 0.004 A. Th e decrease seemed to be real for the apparent uncertainty was not much greater than 0.001 A. (M.C.G.)

Studies were made on the feasibility of effecting diffusion bonding in U, using pure Au as a catalyst, and by solid state diffusion without the use of a catalyst. It was found that the Au appeared to have promising characteristics for catalyzing the diffusion bonding reaction in joining uranium to itself. Phase diagrams are given U-Au, U--Cr, U--Co, U--Cu, U--Fe, U--Mn, and U--Ni alloys. (P.C.H.)

The properties of neutral organophosphorus compounds as solvents, in particular, solvents which form solvation complexes with inorganic molecules, were considered. Physical properties of the compounds are described. Phospnines, phosphine oxides, phosphinates, phosphonates, and phosphates were studied with respect to complex formation with inorganic compounds. The extraction of mineral acids by these compounds is discussed. (M.C.G.)

None

This report details activities of the Fuels Development Operation during the months of July, August, and September of 1962.

Progress Development of a high temperature, vaporfilled thermionic converter for application with a nuclear reactor for space-vehicle electrical power generation is reported. Problems associated with the design and opera tion of a thermionic converter employing a UC-ZrC emitter, a cesium plasma for space charge neutralization, and a high-temperature collector are described. Emitter fabrication techniques are also described. A test cell employing a cylindrical UC-ZrC emitter, which was pressure bonded to a tantalum sleeve, and a low- temperature copper collector, was fabricated and operated for 400 hours to provide experimental data. The emitter was operated at temperatures of the order of 2000 deg C while the collector temperature was maintained at 200 to 300 deg C. A conceptual design for a thermionic power reactor incorporating the thermionic converter under development is also studied. It was concluded that a thermionic fuel element would be about 20 inches long and 0.68 inch in diameter and would incorporate 1O thermionic cells. The load voltage per fuel element would be about 14.5 volts and two elements would be connected in parallel (electrically) to provide an output of 29 volts. The over-all design would provide an electrical power level of approximately one megawatt. (auth)

The analyzer can be operated either internally or externally. The 10 ma germanium discriminator is quiescently biased to 8.5 ma in its low-voltage state. An input signal current of 3.5 ma or more triggers it to its highvoltage state. This triggers the oscillator. The oscillator signal is buffered and mixed in the bridge modulator with the reference radiofrequency signal from the cyclotron. The low-frequency beat note from the bridge moduiator is squared up and passed to the beat zero univibrator which generates 0.7 mu sec signals each time the beat note passes through zero from positive to negative. The trailing edge of the beat zero unlvibrator is employed to terminate the time-of-flight measurement and to control the servo measurement. Drawings are included. (M.C.G.)

None

A solidified-metal seal for possible use in moIten-saIt systems was fabricated and tested on a laboratory scale/su The seal consisted of an 80 Au-20 Cu (wt%) sealant alloy in contact with IN0R-8 base metal/su Eleven successive helium-leak-tlght sealings were effected before termination of the test due to a leak in one of the mating parts/su With better control over the heating cycle and slight modifications in seal design, it is expected that the useful life of a seal of this type could be extended even further. (auth)

None

being developed, which will make it possible to transmit information from 100 or more in-core sensors through a single pressure vessel penetration. The development of a multiplexing subsystem for use within the reactor pressure vessel is being carried out. The most promising methods of multiplexing investigated are electromechanical commutation and electroric frequency division. (M.C.G.)

An experimental program to evaluate the performance of FCR and EFCR fuel during transient operation is outlined, and the initial series of tests are described in some detail. Test results from five experiments in the TREAT reactor, using 1-in. OD SS-clad UO/sub 2/ fuel specimens, are compared with regard to fuel temperatures, mechanical integrity, and post-irradiation appearance. Incipient fuel pin failure limits for transients are identified with maximum fuel temperatures in the range of 7000 deg F. Multiple transient damage to the cladding is likely for transients above the melting point of the fuel. (auth)

Statistical analysis, primarily analysis of variance, was applied to evaluate several factors involved in the development of suitable fabrication and processing techniques for the production of lead telluride thermoelectric elements for the SNAP 10A energy conversion system. The analysis methods are described as to their application for determining the effects of various processing steps, estabIishing the value of individual operations, and evaluating the significance of test results. The elimination of unnecessary or detrimental processing steps was accomplished and the number of required tests was substantially reduced by application of these statistical methods to the SNAP 10A production development effort. (auth)

Activities in a project aimed at the improvement of fuel elements for high flux test reactors are reported. The investigation of new fuel compositions, distributions, and geometries is being undertaken to increase fuel life, to improve the flux distribution, and to provide a means of safely reaching higher reactor operating power and power density in these reactors. The effects of nuclear irradiation on the fuel and structural materials is being studied to predict the performance of these materials in more advanced reactor designs. A summary of the past year's progress is given and the fabrication and irradiation of samples containing up to 50 wt % U--Al alloys, cermets of UO/sub 2/, U/sub 3/O/ sub 8/, UC, UN, U/sub 3/Si, and Al, clad in various Al an d Be--Al materials is described. The use of ThO/sub 2/ and Th cores, the addition of BeO to cermet cores and high density fuei cores of U--Al intermetailics produced by powder metallurgy techniques were studied during the year. High strength APM claddings involving Al/sub 2/O/sub 3/ contents from 8 to 10% were tested and indicate the need for improved quality control of the APM material. Duplex claddings involving burnable poison layers and APM clad …

In this report, approximations which have been shown to simplify the calculation of the normal modes of paraffin hydrocarbons are tested for olefinic hydrocarbons by application to C2H4, CH2CD, C2D4. The results indicate that the method should suffice for the low-frequency models below about 0.1 ev energy, and may be adequate for all vibrations as far as he needs of neutron scattering are concerned,

Experimental determinations of the ionic and electronic emission characteristics of Ta, W, Re, and lr cathodes in vapor thermionic converters are compared. It is shown that Ta provides superior thermal ionization qualities at high pressure compared with W, Re, and Lr. High electronic current densities may be obtained from Cs on Re and Cs on Ir at much lower Cs vapor pressures than from Ta or W. An over-all efficiency of 19% was achieved with a Re cathode at 2440 deg K. (auth)

This memorandum outlines the area of interest in connection with the SSBN launch application, on modification of the Tory II-C control rod system; and suggest a plan of development of information. Because of the very limited space for overall missile length, little room is available for control rod motion upstream from the core. Shortening the rod stroke, and the total length occupied by control rod mechanism., becomes very desirable. Changes in the actuator and linkage mechanism will clearly help, and should be investigated. However, this is concerned only with neutronic aspects.

Ten columns of ripe uranium were discharged and recharged from KE Reactor during operation (first large scale refueling test with Operational Fueling Facility gear). For the last year, many tests were performed in preparation for the ten tube discharge. Objectives of the production test have been met. The system was proved to be feasible; no reactor control problems were encountered by refueling during operation.

This document details activities of the irradiation processing department during the month of December, 1961. Al 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; and NPR project.

This document details activities of the Irradiation Processing Department during the month of January, 1962. 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; and NPR Project.

This document details activities of the irradiation processing department during the month of February, 1962. 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; and NPR Project.

This is the monthly report for the Hanford Laboratories Operation, January, 1962. Reactor fuels, chemistry, dosimetry, separation processes, reactor technology financial activities, biology operation, physics and instrumentation research, employee relations, operations research and synthesis operation, programming, radiation protection, laboratory auxiliaries operation, and technical administration operation area discussed.

The monthly report for the Hanford Laboratories Operation, February 1962. Reactor fuels, chemistry, dosimetry, separation processes, reactor technology, financial activities, biology operation, and physics and instrumentation research, operations research and synthesis operation, and programming are discussed.

This is the monthly report for the Hanford Laboratories Operation, May, 1962. Reactor fuels, chemistry, dosimetry, separation process, reactor technology employee relations, operations research and synthesis operation, programming, and radiation protection are discussed.