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Evidence is presented which points to (at least) two bound forms of bacteriochlorophyll present in chromatophores of Rhodospirillum rubrum, both of them readily converted to unbound bacteriochlorophyll (abs. max. 770 mu) when the chromatophores are extracted with acetone or ethanol. Controlled oxidation of the chromatophores with Ir(IV) or with Zn(II) and ferricyanide preferentially destroys the more strongly absorbing pigment (abs. max. 880 mu) but brings about only a slight decrease in the magnitude of the photoinduced absorption changes at 810 and 792 mu. Such oxidations yield a new pigment, absorbing at 715 mu in the aqueous preparation and, more strongly, at 680-684 mu when the pigment is extracted into organic solvents. This pigment is formed irreversibly and is therefore different from the material formed by photooxidation of chromatophores. Its visible spectrum and the spectrum of the material formed from it by acidification suggest that it is a chlorophyll-like substance, possibly derived from bacteriochlorophyll by (two-electron) oxidation of one of the dihydropyrrole rings to a pyrrole ring. Directions are given for separation of this pigment from other colored compounds present in the oxidation mixtures.

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This report is a descriptive journey of the Acceptance test specifications/procedure for thermocouples.

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The Advanced Reactivity Measurement Facilities, ARMF-I and ARMF-II, are nearly identical critical facilities and are used almost exclusively for measuring reactor physics parameters, such as reactor-spectrum cross sections and resonance integral cross sections. They are, therefore, designed to (a) have large statistical weights for fuels and poisons, (b) be mechanically stable enough to produce reproducible reactivity measurements, and (c) have sensitive instrumentation capable of measuring very small reactivities. These facilities are swimming-pool-type reactors having light-water moderated cores made up of platetype fuel elements containing fully enriched U-235. The facilities are located at the National Reactor Testing Station in Idaho near the Materials Testing Reactor (MTR). Being located near the MTR permits measurements on short- lived fission products and transmuted isotopes. By use of the capsule transfer tube connecting the MTR and ARMF canals, a capsule can be transferred from the MTR hydraulic rabbit to the ARMF and prepared for reactivity measurements in 15 minutes. Both ARMF reactors use a servo-controlled regulating rod for reactivity measurements rather than a pile oscillator. The reactivity effect of a capsule placed in the reactor is determined from the resultant regulating rod displacement. In order to make the regulating rod a precise measuring device, its …

This report addresses details of the Advanced SR-90 Space Power Supply Study

The preliminary evaluation report and transmittal letter rated the Aerojet-General 1963 Contract Year's work on the NERVA program as "below normal" in its overall performance.

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The AIREK-KEWB Program is written in Fortran II to solve space independent reactor kinects equations.

This report has been distributed according to the category "Mathematics and Computers" as given in "Standard Distribution Lists for Unclassified Scientific and Technical Reports" TID

Tabulated are critical masses of simple systems, which have been measured at Los Alamos through the year 1963

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Comparisons of the experimental data on seal pressure distributions obtained from the A-11 Flow Induced Vibration Test, Phases I and III, with analytical results including porous flow through the unimpregnated inner reflector cylinder for the same operating conditions show generally very good agreement. The principal deviations between analysis and experiment occurs when high pressure ratios exist across the last seal. Additional investigation, both in the relationship used in the analytical model and in the experimental area, are required to determine the cause of the deviation found between analysis and experiment when the pressure ratio across the last seal is near critical. As a result of this comparison, it appears that the analytical methods and assumtions made in predicting unheated seal pressure distributions are resonable, and may be used with confidence in the test prediction of the NRX-A1 cold flow test.

This report presents the design significance of the test results and their application to actual reactor operation. In so doing, it complies with the NRX-A2 component test analysis requirements.

The interface seal between the inner reflector cylinder and the nozzle flange prevents coolant flow from bypassing the reflector system and core and flowing directly from the reflector inlet plenum to the core exit.