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Preparation of bismuth powder

Description: The Purpose of this manual is to describe preparation of bismuth powder for use in process operations. Bismuth powder is to be prepared in Room 232 of ``T`` Building where all necessary apparatus is installed.
Date: February 15, 1949
Creator: Cox, G.C.
Partner: UNT Libraries Government Documents Department

Project 9536 HEW Building 105: Conference on welding design and technique

Description: On February 4 at a conference in T.C. Gary`s office attended by Messrs. Wood, Gary, H.T. Daniels, Burns and C.R. Johnson, the design of the strap plates on the front and rear shields of the pile was discussed from the standpoint of welding technique in the field. Discussion of the design centered about the plug welding of the plates to the Laminated blocks and the ability of the field to perform this work properly. It was decided that welding specialists should be consulted prior to the beginning of the actual field erection in order that the best technique could be employed to guarantee good workmanship. It was agreed that a conference with such specialists should embrace both the features of the design as well as the practical phases of welding itself. This report provides details of this conference.
Date: February 15, 1944
Creator: Daniels, H.T.
Partner: UNT Libraries Government Documents Department

Shielded room measurements, Final report

Description: The attenuation of electro-statically and electro-magnetically shielded rooms in the ``E,`` ``R,`` ``I,`` and ``T`` Buildings was measured so that corrective measure could be taken if the attenuation was found to be low. If remedial measures could not be taken, the shortcomings of the rooms would be known. Also, the men making the measurements should oversee construction and correct errors at the time. The work was performed by measuring the attenuation at spot frequencies over the range of from 150 kilocycles to 1280 megacycles with suitable equipment mounted in small rubber-tried trucks. The attenuation was determined by ``before and after`` shielding and/or ``door open and door closed`` measurements after installation of copper shielding. In general, attenuation in the frequency range of approximately 10 to 150 mc. was good and was of the order expected. At frequencies in the range of 150 mc. to 1280 mc., the attenuation curve was more erratic; that is, at certain frequencies a severe loss of attenuation was noted, while at others, the attenuation was very good. This was mainly due to poor or faulty seals around doors and pass windows. These poor seals existed in the ``T,`` ``E,`` and ``I`` Buildings because the doors were fitted improperly and somewhat inferior material was used. By experience from these difficulties, both causes were corrected in the ``R`` Building, which resulted in the improvement of the very high frequency (v.h.f.) range in this building. In some specific cases, however, the results were about the same. For the range of frequencies below approximately 10 mc., the attenuation, in almost all cases, gradually decreased as the frequency decreased and reached a minimum at .3 to 1.0 mc. This loss of attenuation was attributed to multiple grounding caused by moisture in the insulating timbers and will gradually decrease as the wood ...
Date: February 22, 1949
Creator: Stanton, J.S.
Partner: UNT Libraries Government Documents Department

IMPREGNATION OF GRAPHITE WITH URANIUM COMPOUNDS FOR USE AS FUEL ROD MATERIALS

Description: A process hns been developed for impregnating graphite with U/sub 3/O/ sub 8/ in connection with the proposed use of such material for fuel rod elements in the Daniels' High Temperature Pile. The process as developed consists of five steps: Fabrication of the graphite in the desired shape; Pretreatment of the graphite by boiling in water and then firing in helium at 800 deg C; Impregnating the graphite by first evacuating the pretreated material and then admitting an aqueous uranyl nitrate solution whose concentration is etermined by the final uranium content desired in the raphite; Drying the impregnated graphite slowly under quilibrium conditions; and Conversion of the uranyl itrate to U/sub 3/O/sub 8/ by firing in helium at 800 deg C. By this process fuel rod elements have been made which contain as much as 19% U/sub 3/O/sub 8/ distributed uniformly throughout the graphite. The considerations leading to the choice of this process are discussed in this report, together with the alternate procedures which were investigated. (auth)
Date: February 1, 1948
Creator: Kanter, M.A.
Partner: UNT Libraries Government Documents Department

The Site B Foundry (Final Report on Part I of P.A. No. 151-ML-54-2, F.S. 41)

Description: The Site B Foundry is equipped for the melting and casting of tuballoy and its alloys. Castings weighing up to 750 pounds and as long as 40 inches can be made. Melting can be carried out in the vacuum, in inert gases or under fluxes. Heating is by high frequency induction. A description of the generally foundry layout, the furnace construction and operation, and of the auxiliary equipment is given in this report. The casting technique used in the Site B Foundry is designed to minimize piping and cold shuts in the billets. The top of the mold is kept hot and freezing of the billet takes place from the bottom. This hot topping minimizes piping. Controlled pouring into warm molds minimized cold shuts.
Date: February 12, 1945
Creator: Lauletta, Paul
Partner: UNT Libraries Government Documents Department

Monthly Progress Report No. 58 for February 1948

Description: This is a monthly progress report on the following programs: (1) 184-inch Cyclotron; (2) 60-inch Cyclotron; (3) Synchrotron; (4) Linear Accelerator; (5) Experimental Physics; (6) Theoretical Physics; (7) Isotope Research; (8) Chemistry; (9) Medical Physics; and (10) Health Physics and Chemistry.
Date: February 1, 1948
Partner: UNT Libraries Government Documents Department

100 Areas, February 5--February 11

Description: This report gives the weekly status for the B, D, and F piles. Also given is the reactivity status at the end of the week for each pile. Process water control and pressure drop studies are discussed. Finally a brief discussion is given of the graphite expansion problem.
Date: February 15, 1946
Creator: Jordan, W. E.
Partner: UNT Libraries Government Documents Department

100 Areas, January 29 through February 4, 1946

Description: The B Pile operated 25 MW below rated power level without interruption during the week. The D Pile was shut down on January 29. During the shutdown 103 tubes were discharged. The shut down lasted for 15 hours. During operation after the shut down power was reduced to meet graphite temperature restrictions. The F Pile was run steadily throughout the week at 25 MW below rated level. Iron content in the process water averaged 0.015, 0.011 and 0.010 ppm at B, D, and F Areas, respectively. Examination of the slugs discharged from four corrosion tubes at F has been completed. A summary of conditions found in the vertical and horizontal aluminium thimbles at D and F during a recent inspection are given. Results are given on the graphite expansion problem.
Date: February 8, 1946
Creator: Jordan, W. E.
Partner: UNT Libraries Government Documents Department

Site ``W`` description

Description: This site description of the Hanford Reservation from February 1943 gives size, topography, geology, population, water supply, railroad, highway, power, meteorological, and valuation information. Maps are included.
Date: February 15, 1943
Creator: Grady, J. A.
Partner: UNT Libraries Government Documents Department

Hanford Engineer Works technical progress letter No. 138, February 16--22, [1947]

Description: This technical progress letter contains reports from six Technical Department divisions at the Hanford Engineer Works for February 16 through February 22, 1947. The six reporting divisions are: 100 Areas, 300 Area, 200 Areas, Chemical Development, Laboratories, and Statistical Studies. (JL)
Date: February 27, 1947
Creator: Greninger, A. B.
Partner: UNT Libraries Government Documents Department

Graphite expansion committee meeting of January 7, 1947

Description: The fourteenth meeting of the Graphite Expansion Committee was held on February 7, 1947. Laboratory studies indicate that either the graphite thermocouples are reading low or that annealing effects at elevated temperatures within the pile are much greater than those encountered In the laboratory. Current difficulties with operation of some of the horizontal and vertical control rods seem to be attributable to graphite expansion, though no complete understanding of the phenomena has been obtained and one is unable to predict the time required for similar difficulties to develop in other rods. Changes in clearance between process tubes and pile graphite in the D Pile have been erratic in nature but have averaged much less than had been anticipated. The negligible decrease in clearance for central tubes indicates that the expanding cross-wise graphite layers are slipping with respect to the graphite layers which contain process tubes.
Date: February 19, 1947
Creator: Woods, W. K.
Partner: UNT Libraries Government Documents Department

Hanford Engineer Works technical progress letter No. 137, February 9--15, [1947]

Description: This technical progress letter contains reports from six Technical Department divisions at the Hanford Engineer Works for February 9, through February 15, 1947. The six reporting divisions are: 100 Areas, 300 Area, 200 Areas, Chemical Development, Laboratories, and Statistical Studies.
Date: February 20, 1947
Creator: Greninger, A. B.
Partner: UNT Libraries Government Documents Department

300 Area, February 12 through February 18

Description: Extrusion was run on one day, February 2, and a total of 271 billets (178 Type G, 12 type BT, and 81 red band) were processed. Two failures occurred among the red band billets; UM 6610 had begun to melt in the furnace and TX 3323 disintegrated on being extruded through the die. Samples of these billets are being checked chemically and metallurgically in an attempt to ascertain the cause for the hot-short characteristics of these billets. A sample cut from a rod which possessed zero strength (fell apart under no stress other than its own weight) at extrusion temperature was found to contain a large amount of microconstituent not ordinarily found in appreciable quantity on uranium sections. The distribution and appearance of the excess phase suggested at least partial liquation at the working temperature and it could, therefore, be responsible for the hot-short tendency.
Date: February 22, 1946
Partner: UNT Libraries Government Documents Department

The present status of polonium tolerance estimation. Biology seminar, February 1, 1949

Description: Despite the fact the adequate data from long-term, chronic experiments on the effects of Po{sup 210} are not available, some sort of a working figure for the maximum permissible body content of polonium is desirable. As described herein, calculations involved in determining the permissible body content of polonium generally fall into three classes. 1. Comparison of X-ray and polonium toxicity and application of an acceptable X-ray tolerance figure. 2. Assumption of a most sensitive organ and computation of the critical concentration of radioactive material present in this organ under conditions such that the organ received an assumed maximum permissible exposure over an indefinitely long period of time. 3. Comparison of radium and polonium toxicity with application of an acceptable maximal content of radium.
Date: February 16, 1949
Creator: Hackett, P. L.
Partner: UNT Libraries Government Documents Department