This report discusses the conference on direct energy conversion.

The ground-state wave function and energy of a finite system of interacting fermions are expanded in terms of multiple-particle excitations on an uncorrelated zero-order state. The resulting set of coupled equations constitutes a systematic variational generalization of Hartree-Fock theory. Comparison is made with many-body perturbation theory and it is shown that to any order the theory incorporates an infinite number of perturbation theory terms. Solutions of the equations for ground-state atomic systems are discussed and related to previous work using many-body perturbation theory. It is shown that the sums of perturbation terms necessary for convergence are automatically included in the equations for two-particle excitations. Application of the equations to open-shell atoms is described.

The chemical potential of the brine from I.I.D. Well No. 1 was evaluated and reported in Rogers Engineering Coo, Inc. March 1962 Flow Test Report. This evaluation considered only the recovery of sodium chloride, as the prime salable product and alternately as the raw material for conversion to salable chlorine and caustic. Both cases showed low net revenue relative to the estimated capital investment required. The subsequent three month well flow test indicates continued production of a consistent type brine can be expected from this well. Based on the flow and composition data established during this test period, chemical production potential has been examined. The separation and sale of high quality potassium chloride appears attractive. Attached are sketches of each of the two production schemes considered with estimates of capital and operating costs and revenue.

Puromycin, an inhibitor of protein synthesis, appears to act as an inhibitor at additional sites during the induction of {beta}-galactosidase synthesis. No inhibition of the reactions proceeding during the first 20 seconds of induction was observed, but puromycin seems to prevent the accumulation of messenger RNA during the period between 20 seconds and the first appearance of enzyme activity after 3 minutes. When cells from a stationary culture are placed in fresh medium containing inducer for {beta}-galactosidase, growth, as represented by increase in turbidity and by total protein synthesis, starts within 30 seconds. By contrast, {beta}-galactosidase synthesis is greatly delayed compared with induction during exponential growth. Two other inducible enzymes show similar lags, but malic dehydrogenase, which requires no external inducer, shows no lag. The lags are not due to catabolite repression phenomena. They cannot be reduced by pretreatment of the culture with inducer, or by supplementing the fresh medium with amino acids or nucleotides. The lag is also demonstrated by an i{sup -} mutant constitutive for {beta}-galactosidase synthesis. An inhibitor of RNA synthesis, 6-azauracil, preferentially inhibits {beta}-galactosidase synthesis compared with growth in both inducible and constitutive strains. It is suggested that these observations, together with many reports in the …

Dye-macromolecule complexes provide good models for the study of the effects of coupling between chromophores. In addition to modifications of the visible and UV absorption spectra of the dyes at small interchromophore distances, very efficient energy transfer has been demonstrated at longer distances. The probability of nonradiative transition increases with the number of excitation transfers so that an array of oscillators close to one another becomes nonfluorescent. The insertion of a dye molecule, acting as a trap for the excitation energy, in the highly ordered system of chromophores constituted by the purine and pyrimidine bases of native DNA has given results supporting the intercalation model of Lerman and providing an experimental approach to the problem of the path length of energy migration in the DNA molecule. The average excitation path length seems to be of the order of only ten base pairs, a result which can explain the lack of fluorescence of the DNA.

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The instructions described in this procedure are typical of the operation of Test Cell A relative to the KIWI-B4A. Operation of Test Cell A relative to the NRX reactor will require modifications dictated by specific test requirements. Under NRX conditions, it will be the responsibility of the test cell manager to evaluate the capabilities of Test Cell A in terms of given test requirements and then set forth detailed checklists which will be compatible with the test requirements.

It is the purpose of this document to provide the scope of piping changes that are needed to supply gravity-fed water to the reactor storage basins on an unattended basis following complete reactor discharge of metal into these basins.

Progress is reported for the month of October, 1963 in the following research and development activities: Lattice parameter and spectral index experiments; T{sup 3} and Np{sup 237} production rates for a highly enriched fuel loading; graphite heat generation; technical bases; physics study of single tube fuel element; thirty-six tube special 1.25 w/o fuel test loading; and code development FLEX 3.

The KER loops are four pressurized water-cooled in-reactor testing loops in which fuel, coolant and corrosion tests are being conducted for the N Reactor program. Two of the loops, KER-3 and KER-4, are equipped with N-size Zr-2 process tubes and have sufficient pumping and heat dissipation capacity to permit testing of 14-element charges of N fuel. The other two loops, HER-1 and KER-2, are fitted with Zr-2 process tubes of 2.1 in. inner diameter (vs 2.7 in. for N). The small loops can be used to test charges of N inner tubes or other elements sized at about 1.8 in. outer diameter or less. An inert sleeve must be used with N inner tubes to assure adequate coolant flow over both surfaces of the elements. The KE reactor active zone is 28 in. long com pared to 35 in. for N so the length of test charges is somewhat shorter than actual N charges will be. The purpose of this report is to review the testing environment, to discuss the testing program and to present the schedule as presently seen.

A half-plant low alum water treatment test began at F Reactor on January 16, 1963. The test, which had been prompted by the analysis of ledge corrosion attack on fuel elements, will demonstrate whether or not high alum feed is responsible for increasing the frequency of ledge and groove corrosion attack on fuel element surfaces. The effect will be evaluated by comparing visual examination results obtained from normal production fuel irradiated in process water treated with two different alum feed rates. Three 20 column fuel discharges, ten from each side of the reactor, have been taken during the test as follows: (1) One discharge prior to the start of the test. (2) One discharge such that the test side was exposed to coolant treated with both high and low alum feed. (3) One discharge under test conditions. This report presents the results from the second discharge under test conditions.

This monthly technical report details activities in reactor physics research and development during the month of April 1963.

A unique mechanical drive system with associated transistorized circuitry has been developed to allow digital recording on magnetic tape at carrying data flow rates. The present system records on command at rates up to 40 characters per second with a packing density of 200 characters per inch. The output is on half-inch magnetic tape in a format compatible with conventional playback equipment.

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Over the past few years we have developed a system which allows several different liquid hydrogen and liquid deuterium targets to be placed in the electron beam of the Stanford Mark III accelerator and which can be operated from a remote position. The geometry of our scattering chamber requires that the motion (of the various targets into position) must be in the vertical direction, but that the overall height of the system be constant. These requirements are met by using an internal retractable bellows arrangement to raise and lower the target cells. As many as five cells can be used in conjunction with a single reservoir system.

Optimization of the reactor process involves the knowledge of the longitudinal flux distribution on a semicontinuous, routine basis. The nonpoisonous spline was proposed as a way for obtaining flux traverses at any time during reactor operation, in virtually any location in the core. This report summarizes the findings of a feasibility study conducted in conjunction with PITA-18 and thus serves as a termination of the test phase of spline traversing.

The activities included the single tube fuel element study, production losses encountered upon simultaneous irradiation of Np{sup 237}target material, startup measurements of lattice parameters and spectral indices, neutron lifetime in N-Reactor, production estimates for tritium only, FLEX code, etc.

It is the purpose of this document to provide, in one well-referenced manual, a measure of the degree of reliability that may be placed on routine nuclear material transfer measurements within the Chemical Processing Department, and the relative effects of each measurement uncertainty on the various nuclear material balances. Although statistical techniques were used as a tool in analyzing the data, the results have been presented in a form that should require a bare minimum of statistical training to comprehend, Revisions and corrections will be provided as needed.

The objectives of this production test are: 1. To authorize the outage time involved in installing and removing oxidation monitors for the reactors, and 2. To specifically define sample design, spacing of samples in the channels, and residence times to insure adequate routine monitoring of moderator oxidation rates. This production test is concerned with B, C, D, F, DR, F, and H reactors. Similar requirements have been specified in PITA IP-20-I for KE and KW reactors

Work reported includes: Chemical-Metallurgical Processing; Fuel Cycle Applications of Volatility and Fluidization Techniques; Calorimetry; Reactor Safety; Energy Conversion; and Determination of Nuclear Constants.

This summary on various flow induced vibration tests considers the four major types of tests which could accomplish, in part or in entirey, the experimental verification of design concepts for the support system for the NRX-A design.

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Nuclear data, reactivity coefficients, core meltdown and the maximum accident, performance, fuels, economics, safety, Doppler effect theory, and Doppler experiments are discussed for fast power breeder reactors. Separate abstracts are prepared for 22 of the 46 papers presented. The remaining papers were previously abstracted in NSA

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