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In the light of Redox Plant performance since the start-up on 2-3-55, coupled with a review of the technological factors involved in the current flowsheet, a departure from the process program outlined in HW-34882 is herewith presented as an addendum to that document which will also serve to detail the corresponding items in the latest Redox Test Program, HW-35069. The purposes of this document are to: (1) Discuss the need for modifications of the program given in HW-34882, and (2) Present the details of the proposed revisions.

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Using diffusion theory type formulas for the calculation of thermal utilization, and resonance escape probabilities, and in particular those formulas of Rumsey and Volkoff, an effort has been made to correlate experimentally measured bucklings (Exponential Pile Program at Hanford) with those calculated from theory.

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Experimental instrumentation was tested on Operation Upshot-Knothole in an endeavor to improve existing blast phenomena measuring equipment and techniques. Experimental designs tested include a field unit oscillatoramplifier using transistor circuit elements, a subminiature two-wire field unit, a commercially developed Vibrotron gage and amplifier unit, and a frequency deviation multiplier circuit for obtaining increased signal-tonoise ratios. The Wiancko pressure gage was also evaluated more fully. The results of the tests are described. Transistor circuitry was found to be little affected by atomic blast phenomena. (M.P.G.)

Heat transfer coefficients were determined for the eutectic mixture LiF- KF-NaF (Flinak) flowing in forced convection through circular tubes. Heat, electrically generated in the tube wall was transferred uniformly to the fluid during passage through small-diameter tubes of nickel, Inconel, and 316 stainless steel. The variables involved: Reynolds modulus (N/sub R//sub e/), 2300 to 9500; Prandtl modulus (N/sub P//sub r/, 1.6 to 4.0; average fluid temperatures, 980 to 1370 deg F; and heat flux, 9,000 to 192,000 Btu/hr-ft/sup 2/. Forced-convection heat transfer with Flinak can be represented by the general correlation for heat transfer with ordinary fluids (0.5 < N /sub P//sub r/< 100). The existence of an interfacial resistance in Flinak-Inconel systems was established and its composition determined. Preliminary measurements of thermal conductivity and thickness of film were made. The results verify the effect of the film on Flinak heat transfer in small-diameter Inconel tubes. Thermal entry lengths, determined from variations of local heat transfer coefficients in the entrance of the heated section, were correlated with the Peclet modulus. (auth)

This document presents a summary of work and progress at the Hanford Engineer Works for January 1955. The report is divided into sections by department. A plant wide general summary is included at the beginning of the report, after which the departmental summaries begin. The Manufacturing Department reports plant statistics, and summaries for the Metal Preparation, Reactor and Separation sections. The Engineering Department`s section summarizes work for the Technical Design, and Project Sections. Costs for the various departments are presented in the Financial department`s summary. The Medical, Radiological Sciences, Utilities and General Services, Employee and Public Relations, and Community Real Estate and Services departments have sections presenting their monthly statistics, work, progress, and summaries.

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This report covers the examination of nine process tubes, five tubes from B Pile and four from H Pile. Four of the tubes from B File were removed because they were leaking and the fifth was removed because it contained a stuck ruptured slug. Tube 2681-H was removed for graphite mining, tube 2852-H was removed under PT 313-105-14M ``In-Pile Evaluation of 63-S Aluminum Process Tubes,`` and two tubes were removed from channel 0961-H under PT 105-506-E, ``Recirculation of Pile Cooling Water.`` Visual inspection was made of the inside and outside surfaces of the tubes before and after cleaning with cold 10 per cent nitric acid. Samples varying from one to four inches in length were taken from each section and transferred to the 108-B Metallurgical Laboratory for close examination to determine depth of pitting, 72-S cladding thickness, and wall thickness. These determinations were made at specific points in each section on what appeared to be the area of severest attack. It is indicated on six of the tubes where the sample was taken on the circumference of the tube.

The new KW reactor was placed in operation on January 4, 1955, and had been running at relatively low power levels for only 17 hours when it was shut down because of a process tube water leak which appeared to be associated with a slug rupture. After several days of unrewarding effort to remove the slugs and tube by customary methods, it developed that considerable melting of the tube and slugs had taken place. It was then evident that removal of the stuck mass and repairs to the damaged tube channel would require unusual measures that were certain to extend the reactor outage for several weeks. This report documents the work and findings of the Committee which investigated the KW reactor incident. Its content represents unanimous agreement among the three Committee members.

This is the thirty-sixth progress report of the Laboratory for Nuclear Science at the Massachusetts Institute of Technology. Progress during the period of November 30, 1954 through February 28, 1955 is reported.

An instrument was developed to measure nondestructively the lithium content of target slugs for the SRP reactors. The slugs consist of cylindrical pieces of Li-Al alloy, approximately 0.8 inches in diameter and 12 inches in length, clad with aluminum. The instrument utilizes neutron transmission to determine the Li content in the range 3% to 7% Li.

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A list of studies approved at the meeting is given with programs outlined in the appendix. The following topics were discussed: (1) safety; (2) security violations; (3) arrangements made for interviewees with physics training to visit Building 777; (4) procedures written for handling various fissionable materials on a large scale in the fabrication laboratory; (5) backlog of orders at the Laboratory shop; (6) that the limited number of applications do not justify the use of depleted uranium in the Laboratory; (7) that Savannah River Plant can follow Hanford requirements as to the average and variation of U-235 content in sidestream materials; (8) that Laboratory is to supply the various dimensions and tolerances that probably will be required for tubes with spiral ribs; (9) shipping of various dies and aluminium shapes now being held by aluminium fabricators; (10) obtaining proper hydraulic performance of fuel assemblies; (11) preliminary scopes of work covering process requirements for producing natural uranium elements in plate and tubular form; and (12) arrangements to be made to review the Nuclear Metals Program.

The overall process of photosynthesis involves a number of interconnected processes. These processes, which are cyclic with respect to both energy and material, are related at some points to well-known respiratory processes. The carbon-reduction cycle in photosynthesis is now known in detail. All enzymes involved in this cycle have been isolated and the sources of energy required for its operation have been identified in terms of reducing agents and 'high-energy' phosphate. These sources of energy a r e derived ultimately from absorbed light energy which brings about the photolysis of water. Possible mechanisms for this photolysis and for the transfer of energy from the photolysis products to the carbon-reduction cycle are discussed here. Experimental data, in the form of quantum efficiency measurements, are presented and partially confirm the theories proposed for the mechanisms of energy transfer. A diagram of the complete process of photosynthesis containing the several cycles and their relations is presented.