Discussion of laboratory tests to reduce uranium corrosion.

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.

Map of the Mine Mountain Quadrangle in Nye County, Nevada.

This report details activities of the N-Reactor Department during the month of September 1964.

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Production Test IP-546-A. consisting of 20 charges for the purpose of irradiating the first hot die sized fuel elements was charged in C-Reactor July 27, 1963. A second tests PT-IP-616-A containing a total of 19 charges had been charged on two separate outages; 13 land 6 tubes on September 28, 1963 and October 30, 1963, respectively. Fabrication of test quantities was becoming more routine and additional irradiation tests were planned. This report summarizes the fabrication of hot die sized fuel elements originally intended for Production Test IP-630-A, but changed to ``Supplement ``A`` to Production Test IP-546-A, Irradiation of Diffusion Bonded Fuel Elements,`` HW-75465 E. The production test was changed due to unexpected growth behavior of hot die sized fuel during irradiation.

During the major part of October the N-Reactor was shut down for dump condenser repair, scheduled maintenance and equipment modifications. Work on dump condensers was successfully completed and the construction and tie-in of steam generator cell No. 4 was accomplished. Power ascension was initiated on October 24 and the N-Reactor in now operating with all five steam generator cells in full service. Process physics, in-plant testing, and technical activities are described in this document.

Highlights include production program and development program reviews at the Mallinckrodt Chemical Works, and production and development at the National Lead Company of Ohio. Activities at the Savannah River Plant are briefly discussed. General Electric at HAPO reports from the irradiation processing department and the N-Reactor department. The Hanford laboratories report on fuel element work.

Introduction: Contract AT(04-3)-400 provides for the construction of the Stanford Linear Accelerator Center (SLAC), a laboratory that will have as its chief instrument a two-mile-long linear electron accelerator.

The irradiation performance of Zircaloy-2 clad thorium-uranium fuel elements under water-cooled power reactor conditions continues to be excellent. Fuel swelling continues to be no more than that required to accommodate the fission product atoms. Measured fuel swelling is less than one percent at 3.1 {times} 10{sup 20} fissions/cc (9,300 MWD/T). The addition of iron and aluminum to metallic uranium fuel elements has been shown to markedly decrease fuel swelling. The improved swelling performance is attributed to a decreased tendency to form mechanically induced porosity and is believed to result from the dispersed second phase particles inhibiting the movement of structural defects formed as a consequence of the anisotropic growth of alpha uranium.

From introduction: This task was conducted at Project Shoal to observe the response of simulated Dribble area building foundations to ground motions induced by a nuclear detonation.

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Introduction: The Mobile Gamma Irradiator is a semi-production demonstration unit capable of being transported from one area to another for use in irradiating fruit and farm produce, with the capability of furnishing dosages in the pasteurization range.

This report on the RFD-1 optical data and external fuel-element experiment includes a description of the instruments and test components used, a presentation of the data obtained, an explanation of the methods of data reduction employed, and a statement of the conclusions derived. It covers the theory, design, qualification tests, flight-test data, and results of the external fuel-element experiment. Also presented is a theoretical analysis of observed versus predicted ablation times and altitudes for the external fuel elements. In addition, this report presents recommendations for improvements to data acquisition and reduction methods in future, similar flight tests.

Abstract: Design charts and systematic design forms are presented for simplified calculations to check the number of convolutions and thickness required to limit the deflection and pressure stress range in three types of bellows.

Candidate canning materials were tested in contact with molten stand-ins for Pm metal; nondestructive tests were conducted. Related studies included americium processing, uranium-233 support, Ce-Pm separation, and technetium analyses.

The monthly report for the Hanford Laboratories Operation, September 1964. Reactor fuels, chemistry, dosimetry, separation processes, reactor technology, financial activities, biology operation, and physics and instrumentation research, and applied mathematics operations are discussed.

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This report, for September 1964 from the Chemical Processing Department at HAPO, discusses the following: Production operation; Purex and Redox operation; Finished products operation; maintenance; Financial operations; facilities engineering; research; employee relations; weapons manufacturing operation; and safety and security.

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Hot die sizing (HDS) is a process being investigated to replace the existing AlSi brazing process. Hot die sizing consists of sizing a nickel-plated core and aluminum can assembly with cold dies to produce a diffusion bonded aluminum clad fuel element. Upon completion of fabrication of the first natural uranium hot die sized fuel elements for production test IP-546-A, the next step in evaluation of the process was to assemble enriched fuel for further irradiation testing. This report summarizes the fabrication of 0.947% U-235 enriched fuel elements for ``Production Test IP-616-A.``

With recent concern for downcomer capacity at most areas, it seems appropriate that a survey be made to determine what instrumentation and data are available. The following is a brief description of the available instrumentation and data for KE, KW, H, F, DR, D, C, and B reactors.