This is a progress report of the production reactors on the Hanford Reservation for the month of December 1951. This report takes each division (e.g., manufacturing, medical, accounting, occupational safety, security, reactor operations, etc.) of the site and summarizes its accomplishments and employee relations for that month.

Uncontrolled boiling of the water in a process tube might result in serious damage to a pile. Consequently, it is desirable to maintain header pressure generally sufficient to sweep out any steam which might be formed. Since the header pressure required to remove the steam depends upon the power output of the tube, the power level of a tube or pile is limited by the pressure available. In the past, tube power limitations have been specified and interpretations thereof. Recently a through study, both theoratical and experimental, has been made to determine the validity of these limitations. The purpose of this report is to present the results of the study must make recommendations for future operations. The limits presented herein are based on tube power levels.

None

Tests indicate that of the various alloys tssted for corrosion resistance when exposed 10 an HF-HP atmosphere at 1070 F, the Cr-Ni alloys, as a group, give the best corrosion resistance where strength at high temperature is desired. Other alloys have given excellent results but the lack of strength at the higher temperatures or cost, is against their use in production equipment. (auth)

The amount of hydrogen normally present in zirconium and zirconium alloys suffices to reduce their ductility greatly in an impact test at room temperature, after slow cooling from 6OO deg F. Quenching from 6OO deg F or above gives high impact strength, as does removal of hydrogen by hightemperature vacuum aanealing. The evidence on hydrogen embrittlement, the diffusion, solid solubility, and equilbrium pressure of hydrogen in zirconium the microstructure, and the effects of hydrogen and heat treatment on the mechanical properties of zirconium are discussed. (auth)

The results of a study to determine reliable heat transfer data for the design of a suitable heat exchanger for the Intermediate Scale Homogeneous Reactor are presented. Design studies of a vertical submerged-tube evaporator with nucleate boiling from the outer tube surfaces and of a vertical tube, forced-circulation evaporator are presented in detail. (M.P.G.)

None

None

Thorium Research. The effect of quenching temperature on the hardness of Th--C alloys is described. The effect of quenching temperature and oxygen content on the hardness of Th--O, alloys is discussed. The effects of Be, Cr, and C additions on the properties of pure Th are described. The mechanical properties, recrystallization, and fabrication of Th are given. Preferred Orientation of Uranium. Fabricating conditions, preferred orientation, and examination of alpha-extruded U rods are given. The creep rate of beta-treated normal U and of extruded Th is given. Properties of some high-temperature brazing alloys are given. Welding conditions are given for cone-arc welding of stainless steel tube-to-header joints. Homogeneous Reactor Program. Analysis of various compacts containing B/sub 4/C are given. Preliminary work on the variables involved in welding Ti was started. Experimental work to determine the effects of various impurity elements on the impact properties of Ti and Zr was started. A metallographic examination of Ames Th cold worked and annealed for 60 minutes is presented. Experimental Plate-Cladding Program. The cladding of Th and U with Zr is discussed at length. The cladding of Th with Al is described. Experiments on welding of Th, U, and Zr plates are presented. (W.L.H.)

In accordance with the request of last week, the authors have made a review of the basis for the proposed water plant and pile modifications for the DR and H piles. The engineering review was made and comments are attached. As a result of this review, the author is submitting the following comments: (1) An average power level slightly above that obtainable from the proposed modification may be obtained by the substitution of enlarged pigtails. This latter modification could be accomplished for about 1/3 the capital cost and will permit operation with a header pressure approximately 100 psi lower, thus reducing power consumption. (2) The shutdown period required for installation of the ball third system may allow sufficient time for both the installation of enlarged pigtails and water plant modifications. (3) It is their understanding that the enlarged fitting were not included within the scope because cost, time, and corrosion limitations would not allow power increases. Shutdown schedules were based on the assumption that only one crossheader could be removed at one time. They do not believe this is realistic. (4) In general, they feel that a sound basis has not been demonstrated for the course of action proposed. This …

This document is a compilation of obsolete security codes, convenience codes and local jargon in use, or previously used, at Hanford Works. It is compiled to aid readers in understanding the Hanford report literature, particularly that originated in the early years of the Project.

This memorandum details the recommendation of the Technical Section that the C Pile be started up using alum treated water to which has been added sodium dichromate at a concentration of 2 ppm., and that the pile be purged at monthly intervals despite the expected absence of film formation. During the initial months of operation the necessity of adding sodium dichromate and of purging the pile should be evaluated with the hope that these factors can be eliminated from the process. The reasons for this recommendation, and proposals for water treatment in the current operating piles are discussed.

The Reactor Safeguard Committee formula for the allowable minimum distance between a reactor and the public domain is expressed as: r = 0.01{radical}P, where r = radius from reactor in miles, and P = reactor power level in kilowatts. The six plates in this report illustrates the application of this formula for Hanford Works, both for individual reactors and all reactors in an area.

This constitutes a review of the path of carbon in photosynthesis as it has been elaborated through the summer of 1952, with particular attention focused on those aspects of carbon metabolism and i t s variation which have led to some direct information regarding the primary quantum conversion act. An introduction to the arguments which have been adduced in support of the idea that chlorophyll i s a physical sensitizer handing i t s excitation on to thioctic acid, a compound containing a strained 1, 2 -dithiolcyclopentane ring, i s given.

A method is described for the preparation of PuF/sub 3/ by means of a solid phase-gas reaction between Pu(IV) oxatate or Pu(III) oxalate and Freon-type compounds such as CC1/sub 2/F/sib 2/. (auth)

None