Three techniques were employed in measuring the fission rate of the STE (SNAP Shield Test Experiment) fission source plate; the thermal neutron absorption rate, power dissipation (calorimetric method), and the fission-neutron production technique. The results obtained, when weighted according to the reciprocal of the squares of the estimated errors, yielded a fission rate of 1.97 x 10/sup 12/ fissions/sec plus or minus 4% for a STE reactor power level of 50 kw. Assuming that 190 Mev of usable energy is liberated per fission of U/sup 235/ , this fission rate corresponds to a fission-plate power of 59.9 watts plus or minus 4%. The calorimetric calibration technique proved to be the most satisfactory of the three techniques used. The design of the STE fission source plate allowed the plate to be enclosed completely in fiberglass insulation and heated electrically as well as by nuclear means. The heating rate is sufficiently high that errors caused by ambient temperature changes are negligible. Details of the three calibration techniques employed are given. The average fission-plate power per unit area was determined to be 2.05 x 10/sup -2/ watts/cm/sup 2/ plus or minus 4%, or about 14 times that of the Oak Ridge National Laboratory …

Progress is reported on preparation of EBWR for highpower operation, development and operation of Borax-V, research and development on liquid metal reactors including ZPR-III, ZPR-VI, ZPR-DS, EBR-I, EBR-II, and FARET. Developments in general reactor technology are reported in physics, fuels, heat transfer, and chemical separations. Developments in advanced research are reported on reactors and direct conversion devices. Work in the area of nuclear safety is also reported. (J.R.D.)

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.)

A table of functions is presented that simplifies the evaluation of the Debye-Waller factor which gives the fraction of recoil-free gamma ray processes in Mbssbauer effect studies. A graph of the recoil-free fraction, f, as a function of the ratio of the Debye temperature to the crystal temperature for selected recoil energy to Debye temperature ratios is included for rapid estimation of f. (auth)

A noncanonical transformation of the boson creation and annihilation operators is performed in order to obtain a Hamiltonian which can be treated by the standard methods of field-theoretic perturbation theory. The standard results of Belyaev (with a slight modification) are rederived by this technique. (auth)

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)

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.)

Items of significant technical progress which occurred in specific reactor projects and in general engineering research and development programs are reported. Specific developments are reported concerning the EBWR, Borax-V, EBR-l and II, and the Fast Reactor Test Facility (FARET). General research and development is reported on evaluation of carbide and oxide fuels, isotopic power sources, metallography of fissium alloys, ZPR III, VI, and lX experiments, and Juggernaut critical experiments. Developments in general reactor technology are reported in the areas of applied reactor physics, fuels, materials, and components development, heat engineering, and separations. Other work is reported on direct conversion devices and in the area of nuclear safety. (J.R.D.)

A procedure was developed for preparing high-purity magnesium oxide for use in growing single crystals needed in studies of radiation effects. The procedure consists in dissolving high-purity sublimed magnesium metal in nitric acid, extracting impurities from the solution into a TTA--Hexone solution, precipitating magnesium carbonate from the aqueous phase, and igniting the magnesium carbonate to magnesium oxide. Amounts of magnesinm oxide from gram to pound quantities can be prepared. (auth)

ABS>Research and development progress is reported on water-cooled reactors, liquid metal-cooled reactors, general reactor technology, plutonium recycle, advance systems research and development, and nuclear safety. Topics covered include the EBWR, BORAX-V, EBR-I, EBR-II, FARET, applied reactor physics, reactor fuels development, reactor materials development, reactor components development, heat engineering and fluid flow, chemical separations, Argonne Advanced Research Reactor, subcritical reactor as substitute for isotope sources, thermal reactor safety studies, fast reactor safety studies, and direct conversion studies. (M.C.G)

Technical progress is reported on specific reactor projects and on general engineering research and development programs. Developmental activities are reported on the EBWR, Borax-V, the liquid metal cooled zero power experiments, EBR-I EBR II, and FARET. In general reactor technology, research is reported on applied reactor physics, reactor fuels development, reactor materials, and chemical separations. In advanced systems research and development, work is reported on the Argonne Advanced Research Reactor and on direct conversion. Safety studies are reported on thermal reactors and fast reactors. (J.R.D.)

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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)

Tin-- aluminum base coatings applied by a cold spray-hot vacuum diffusion technique were studied further on Ta-10 W and Ta-10 Hf-5 W and work initiated on Ta--30 Nb--7t/2 V. Refractory additions to the coatings were optimized for Ta--10 W and the use of aluminum-silicon in tin was found beneficial for Ta--30 Nb--7 1/2 V. Furnace and oxy-acetylene torch tests were performed at temperatures from 1100 to over 3000 deg F. Diffusion treatments in vacuum, hydrogen, and argon were compared for coatings on Ta-10 W. Oxide formation on Ta--10 W coatings at various temperatures was studied by x-ray diffraction. The oxidation behavior of various tin--aluminum alloys and of the intermetallic (Ta--30 Nb--7 1/2 V) Al/sub 3/ was also studied, together with interactions of three alloys with A/sub 2/O/sub 3/ at elevated temperatures in vacuum. (auth)

Research progress is reported on water-cooled reactors, liquid-metal- cooled reactors, general reactor technology, plutonium recycle, advanced systems research and development, and nuclear safety. (M.C.G.)

Revisions to Vol. IV of the PL final design report are presented. The changes presented are exclusively in the mechanical and structural design of the core. Most design changes were dictated by fabrication experience or experimental test results. A complete list of the revised drawings is included. (J.R.D.)

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

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,

This volume is one of twenty-one summarizing the Aircraft Nuclear Propulsion Program of the General Electric Company.