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The development and testing of a demonstration brushless alternator for the ML-1 mobile nuclear power plant is described. The brushless concept was selected after it became apparent that a conventional power generator could not satisfy the ML-1 weight and size requirements. The demonstration alternator fabricated and tested under this program did not meet all performance specifications; the efficiency was low and the unit could not be operated for significant periods of time without overheating. However, a large body of useful data was accumulated during the extensive development program. Of special interest are data on the rotor and stator design, the cooling requirements and on the distribution of eddy current losses. Analysis of the data indicates that a brushless alternator, only slightly larger and heavier than was specified for the ML-1, could be developed with a modest additional effort.

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.

Phosphorus pentoxide reacts with ether to form bicyclo-tetraphosphate ester (II), cyclotetraphosphate ester (III), isocyclotetraphosphate ester (IV), and tetraphosphate ester (V). Phosphorus n.m.r. measurements show the content of the mixtures. The so-called 'ethyl metaphosphate' (Langheld ester) is a mixture of III (50% to 45%), IV (36% to 25%), and V (14% to 30%).

The prebiotic synthesis of phosphorus-containing compounds--such as nucleotides and polynucleotides--would require both a geologically plausible source of the element and pathways for its incorporation into chemical systems on the primitive Earth. The mineral apatite, which is the only significant source of phosphate on Earth, has long been thought to be problematical in this respect due to its low solubility and reactivity. However, in the last decade or so, at least two pathways have been demonstrated which would circumvent these perceived problems. In addition, recent results would seem to suggest an additional, extraterrestrial source of reactive phosphorus. It appears that the 'phosphorus problem' is no longer the stumbling block which it was once thought to be.

The decay kinetics of the photo-induced absorbance changes in red and green algae are very sensitive to the wavelength of the actinic 11ght. A four to twofold increase in half-decay time is noted in going from short wavelength (550-650 mu) to long wavelength (> 700 mu) excitation. The slow decay ratios, produced by long wavelength light can be enhanced with a steady background of short wavelength light. A relationship between initial decay rates and 02 evolution rates is described. This relationship allows a direct correspondence between these spectroscopic studies and the 'red-drop' and 'enhancement' experiments of Emerson.

Operation of the present accelerator is summarized and plans for a new injection system and additional machine modernization are described. Research results of both experimentalists and theorists are reviewed in very brief summaries; references are provided. (RWR)

Work was continued on the development of a process for the gasification of bituminous coal with heat from a nuclear reactor. Major objectives of the project are: (1) develop and test components for a gas-cooled reactor system that can heat gases to 2000/sup 0/ to 2500/sup 0/F; (2) investigate coal gasification methods compatible with this system; and (3) develop an exchanger that can utilize high-temperature heat to gasify coal or heat chemical process streams. During the past year, work was concentrated on the design, construction and installation of a fluidized-bed gasifier in the high-temperature heat system. Design of the fluidized-bed gasifier was based on information obtained from laboratory and pilot-scale gasifiers. The gasification chamber, a length of 6-inch, schedule 80 stainless steel pipe, is fitted with ten 1/2-inch Hastelloy-X tubes running lengthwise. Hot helium flowing through the 1/2-inch tubes provides heat for the gasification of the steam-fluidized char in the 6-inch pipe. Helium leaving the gasifier generates the superheated steam required for gasification. Fabrication and installation of the gasifier was completed and shakedown runs started. In the gasifier, the heat-exchanger tubes will be heated to 1900/sup 0/F in a mixture of the corrosive gases, including H/sub 2/, CO, CO/sub 2/, …

Objective of this test is to authorize irradiation of depleted uranium in a smaller Hanford reactor.

This document provides details of the investigation of the H Reactor mischarging incident.

The fundamental objective of the graphite temperature limit is to prevent excessive oxidation of the graphite moderator blocks with carbon dioxide and water vapor in the reactor atmosphere. Laboratory tests have shown that 10 percent uniform oxidation of graphite results in a loss in strength of approximately 50 per cent. This value of a strength loss of 50 percent has been arbitrarily established as the limit to graphite oxidation over the lifetime of the reactor stack. This limit has been further arbitrarily interpreted as an oxidation rate of not more than two percent per thousand days of reactor operation. At this rate limit, the reactor stack could be operated for 15--20 years before the graphite strength was reduced 50 percent. As with any chemical reaction, the rate of reaction of graphite with oxygen, carbon dioxide, and water vapor increases with increasing temperature. The graphite temperature limits presently in effect at the smaller reactors were therefore primarily established to hold the reaction rate between graphite and carbon dioxide at two percent per thousand operating days and were based on laboratory and in-reactor experiments which are presently believed to have been partially contaminated with oxygen from air leakages. It is therefore the …

The 02 Research and Development program for the Irradiation Processing Department is contained in seven 189-forms, R-1 through R-6 and M-1 and M-2. The subprograms designated by R pertain to reactor research and development, and those designated by M pertain to the metallurgy or the fuels research and development. This report covers the progress in each of the subprograms on an individual basis and follows the format proposed by RLOO. Although the reports are brief, the results are presented in a semitabular form and are essentially complete. Only the activities of the first four months of the fiscal year are included. It should be noted that the over-all IPD program is based on a nearly uniform expenditure of funds over the entire year and the expenditures to date reflect this general pattern. A number of items are listed in the reports on the subprograms that have been performed on product cost funds but were made possible by the research and development effort.

The amount of enriched uranium to support various type of target elements was determined in the Hanford Test Reactor. This report describes the measurement of separate and striped loadings for canned thorium oxide, bismuth, lithium-aluminum, and, in addition, bare depleted uranium. This experiment was undertaken to provide information needed to estimate the E-metal requirements in a production reactor when replacing natural uranium with target material. The amount of enriched uranium which is required to maintain the reactivity in support of target materials must be known to properly predict total reactor reactivity. Danger coefficient measurements were made during original startup tests to provide this information. However, fuel dimensions have changed and new target materials have been introduced which have not been tested in this manner. The target of particular interest at this time of thorium oxide.

This report provides the Redox Operation material balance and production for fiscal year 1965.

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Irradiation tests of aluminum-lithium co-producer target elements are planned for charging in the N-reactor. Although the target elements are subjected to extensive non-destructive testing to assure that defective pieces are not charged, it is necessary to have some knowledge of the failure characteristics of the targets under reactor conditions. To study the possible behavior of in-reactor failures, a series of defected test elements were tested in the high temperature, pressurized TF-9 facility located at 100 KE. The test objectives were: to follow the progress of the failures of target elements with several types of intentional defects, and to run the tests until, on several of the elements, the failure and corrosion had progressed essentially to a point of total destruction of the core. This report describes the intentionally defected elements used in the test and the progressive results of subjecting these defected elements to high temperature water.

This report presents additional justification for operating costs of the Separations Research and Development Program which consists of eleven identifiable activities in four general areas of effort. The activities and their proposed levels of effort are listed. For each of the identifiable activities, the major accomplishments of the last year are listed, together with the proposed goals for the next two years, in the following pages. Significant trends in the program are noted.

A number of tests have been performed and reports issued concerning the adequacy of the last-ditch cooling systems at the Hanford small production reactors. At the present time, re-evaluations are being made, both theoretical and experimental, by process engineers and others at th particular reactor sites. In the interest of uniformity and consistency, this report presents a means of determining the last-ditch cooling adequacy for all the small production reactors. This method includes both the night tanks and the export system.

Some refinements have been introduced into the hot press canning of internally and externally cooled fuel elements. This report outlines the specifications for the process including these refinements. Specifications cover components, dies, and punches, furnace condition, nickel plating, component cleaning, component assembly, sizing, hot pressing and inspection.

The flexibility of N-Reactor will be demonstrated by comparing (in tabular form) the basic 4000 Mw Pu-only, weapons grade case with a 4800 Mw co-product, weapons grade mode including production of Po-210 and PU-238. The competitive position of N-Reactor in the AEC complex will be illustrated in a table summarizing 1964 production studies.

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