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100 Areas technical activities report, engineers - March 1951

Description: This is the monthly 100 areas technical activities report from the engineering division for the month of March 1951. It reports on engineering activities related directly to the different production reactors, and gives progress reports on various engineering projects which are in development by the engineering group.
Date: April 1, 1951
Partner: UNT Libraries Government Documents Department

A concrete shield-design

Description: It is shown that the use of Iron-Limonite shielding concrete and a steel frame structure can afford a saving of $1,351,000.00 when compared to 105 DR-H construction and material costs. C-431-B costs are not complete enough to use as basis except for the concrete materials. This study is based on actual records where possible and shows direct costs only. No allowances for transportation or tooling have been allowed in either case. An overall time saving on reactor shield construction of 30--60 days may be possible, but no significant change in the field erection time is anticipated.
Date: August 14, 1951
Creator: Jaske, R. T.
Partner: UNT Libraries Government Documents Department

Vertical rod temperatures

Description: An important factor affecting the decision on the use of a seal around the VSR on ``C`` is the temperature at which the rod can be expected to reach. Also the temperature of the rod-tip affects the choice of tip moderating material. These temperatures are calculated for a given set of conditions for ``C`` pile. The results of the calculations are best seen by referring to the attached figures. The affects of emissivity and weight of rod can be estimated by comparing the proper curves. The assumed conditions for calculating each curve are important and therefore, the basis for each curve is given separately.
Date: August 14, 1951
Creator: Roy, G. M.
Partner: UNT Libraries Government Documents Department

Expansion of Hanford Works facilities

Description: This report discusses the feasibility of designing and building two 100 Areas at the Coyote Rapids site on the Columbia River. It incorporates the individual studies prepared by the Power and Mechanical Division-HDC-2241, Reactor Division-HDC-2239, Project Engineering Division-HDC-2244, Principal Engineer and HDC-2242, and the Engineering and Construction Services Division-HDC-2243, each outlining the proposed course of action and requirements for that facet of the contemplated work in which they are primarily interested.
Date: June 28, 1951
Creator: Parker, J. S.
Partner: UNT Libraries Government Documents Department

G.E. Co. Hanford Works - Project C-431-A production facility - Sec. A, subcontract G-363, revised design report

Description: The 100-C project is to be located adjacent to the present 100-P Area. It is planned to build an addition to the present 181-B River Pump House using the same elevations for pump settings, intakes, and floors as for the present pump house, thus maintaining the same suction conditions and flood protection as B Area. The 105 Building will be located on higher ground than B Area and, therefore, protection against possible flood damage is assured.
Date: March 29, 1951
Partner: UNT Libraries Government Documents Department

Capacity survey -- Separations Division

Description: Recent tentative production forecasts indicate that as much as 96.6 Kg plutonium, associated with 190 tons uranium, may be produced each month. The ability of the Separations facilities to process these materials is herein summarized. The Redox Production Plant capacity has been reasonably predicted at about 112 tons uranium per month; this rate assumes only that critical mass control is achieved by the limitation of the possible volume accumulation at any point, and that the product concentration step has been modified to permit the greater capacity. At 600 MWD/T (522 g/t) then, the 112 tons uranium per month capacity limits the plutonium output of the plant to 58.5 Kg per month at 80% operating efficiency. The remaining 38 Kg plutonium per month may be processed in the B and T BiPO{sub 4} plants at an operating efficiency of 89.5%; if this operating efficiency cannot be realized, the postulated production rate may be met by either an increased Redox efficiency or by accepting an increased plutonium waste loss of 1% on some portion of the BiPO{sub 4} production.
Date: June 28, 1951
Creator: Frame, J. M. & Tomlinson, R. E.
Partner: UNT Libraries Government Documents Department

Horizontal control rods for ``C`` Reactor

Description: A meeting was held on May 17 to review possible alternate designs of horizontal rods for 105-C. The system used on ``C`` must operate satisfactorily at an anticipated graphite temperature of 380 C (760 F) with the possibility expressed by the Technical Division that this temperature limitations may be raised if satisfactory new pile atmospheres can be developed. The design will be based on a maximum graphite growth of 3 inches at a distance of 3 feet from the edge of the graphite block. This value ignores the anticipated favorable results from graphite coring, and is greater than the growth expected in ``C`` based on experience with present reactors. A satisfactory rod end seal configuration is required for these conditions. It was decided that a round control rod with external seal would be recommended to meet these conditions.
Date: May 21, 1951
Creator: Grantz, H. E.
Partner: UNT Libraries Government Documents Department

Increased water flows and pressures to 105 buildings

Description: Document HW-21096, inquires regarding changes in equipment, so that various proposed flows of process water to each of the present production units, at several 105 control room pressures, may be effected. The proposed conditions are shown in table form in the report. For the purpose of calculations upon which this letter is based, the pressure used here is that which is recorded at the 105 control room ``inlet`` panel. It is actually the top of riser pressure, plus static head between the recorder and the point of pressure tap.
Date: July 27, 1951
Partner: UNT Libraries Government Documents Department

Tentative design basis new 100 Area water plant embodying a close cooling water circuit

Description: The attached document includes a plot plan, flow diagram and delineation of basic assumptions upon which the report was developed. It summarizes the work which has been accomplished to date under RDA No. DC-6 in developing a recirculating water system to serve a new reactor. In order to proceed with the work under RDA No. DC-6 it has been necessary to make certain basic assumptions relative to the primary circuit requirements of RDA No. DC-3. These assumptions are explained in the report and are presented by the exhibits contained therein. Subsequent to the compilation of the basic report certain additional considerations have come to the authors attention and are included in the addendum.
Date: November 14, 1951
Partner: UNT Libraries Government Documents Department

Pile water modifications at DR and H Areas for increased production facilities

Description: A detailed study was undertaken to investigate the feasibility of modifying the front and rear face piping at DR and H Areas to permit increased production rates. This study is in conjunction with a larger investigation concerning methods of increasing plant production facilities. The results of the subject study indicate that approximately one year would be required for the design, procurement, and delivery of critical materials, and that the estimated construction shutdown time to complete each unit is 50 work days on a three shifts basis. Although the length of time required to perform the proposed construction work is not in line with the planned 30 day shutdown period, it is believed that the 50 days reflected by this estimate is realistic and necessary. A critical material schedule, design schedule, construction schedule and force requirement charts are presented on pages 9 to 13 inclusive.
Date: October 4, 1951
Creator: Andersen, R. K.
Partner: UNT Libraries Government Documents Department

Interim report No. 1 on Production Test 105-407-P -- Pile test of magnesium front dummies

Description: The inlet portions of pile process tubes, which originally contained a pattern of aluminum dummy slugs, have been reported subject to pitting corrosion since the removal of the slugs. This corrosion is more severe than that found in the other portions of the tubes. The insertion of magnesium dummy slugs has been recommended to arrest this corrosion. A pile test of the effect of magnesium dummies is in progress and preliminary results are reported. Current-voltage relationships between magnesium and aluminum have been found to be satisfactory. A study of previously reported data on front tube corrosion has been made. It is concluded that the overall corrosion of the tubes is low, but that pitting is occurring in the inlet portion. This pitting is not necessarily the result of removal of the front dummy pattern. Magnesium dummies, when tested, were found safe for the aluminum tubes, but no data were obtained as to their ability to protect the aluminum. The tubes are not considered to be in imminent danger of failure, and if a dummy pattern is inserted it will probably result in a small production loss.
Date: December 18, 1951
Creator: Lewis, M. & Goldsmith, S.
Partner: UNT Libraries Government Documents Department

Filter capacity tests

Description: Increases in production rates in the 100 Areas have caused a demand for additional amounts of cooling water for process use. Consequently, continual efforts have been made to push the existing filter plants well beyond designed capacity. The latest and most successful effort was made at the 100-B filter plant during the spring of 1951. Tests of the 100-B Area indicate that the 100 Area filters can be operated safety at 3,400 GPM per unit, or 13.3% beyond the designed capacity, during the period of most difficult water treatment (February-June). By extrapolation of the data to the most favorable water treatment periods (August--January), it is indicated that net water available for production use is approximately 5% above 3400 GPM. It is recommended that no additional filter plant capacity be installed in existing areas until anticipated water loads exceed 3,400 GPM per filter basin unit. It is further recommended that an investigation be made of the feasibility of changing water flows to the piles on a seasonal basis to take advantage of the fact that the season requiring the greatest theoretical quantity of water (because of high raw water temperatures) is also the season during which it is easiest to produce the greatest quantity of water.
Date: June 29, 1951
Creator: Conley, W. R.
Partner: UNT Libraries Government Documents Department

Interim report No.1, PT-105-403-P, installation and initial operation

Description: The effect of temperature on the properties of graphite is being determined by exposing samples to pile neutrons at controlled temperatures in the range 75 C to 225 C. The first series of samples were charged into the newly installed dry, water-cooled test channel at B pile on January 23, 1951. This report presents details of the charging operation and observations noted during the initial operation of the test.
Date: February 7, 1951
Creator: Haussler, W. M. & Purcell, R. H.
Partner: UNT Libraries Government Documents Department

Insulating webbing between thermal shield and graphite reflector

Description: The purpose of this document is to present the bases and calculations which resulted in the conclusion given in the letter of October 17. Also, the original calculations were made on the basis that the webbing face thickness is equal to 1/2 inch, which is no longer the case. The new thickness is 3/4 inch. This alters the condition of heat generation. Consideration is given to the heat generation in the legs.
Date: October 24, 1951
Partner: UNT Libraries Government Documents Department

An analysis of the suitability of various coring patterns for inclusion in ``C`` Reactor

Description: Preliminary meetings on coring of the graphite have been held with interested parties of the Technical and Production Divisions at which time the advantages and problems of coring were discussed. The advantages and the problems which must be surmounted in order to core have been presented to the working committee. A study of the means of accomplishing coring has been made considering only the central and maximum fringe coring. It is important that the minimum and maximum coring be established as soon as possible so that the coal coring pattern can be worked out and the design completed. From the studies that have been made thus far the 10 mil center core-60 mil fringe core appears to be the most favorable choice. The advantages and disadvantages of several possible coring combinations (central to fringe) are tabulated. The statements and graphs of temperatures made in this tabulation are based on the results of the analogue tests. The estimates of pile expansion resulting from various coring patterns are based on report HDC-1987 by R.K. Andersen. These results are summarized in Figures 1, 2, and 3. The results of the analysis which Technical plans to make on the DR graphite sample will be compared with what would be predicted from this study.
Date: April 13, 1951
Creator: Roy, G. M. & Andersen, R. K.
Partner: UNT Libraries Government Documents Department

Vernatherm functional test, Test Project No. 14

Description: The Vernatherm unit is a temperature sensitive capsule which translates temperature change to mechanical movement of a brass plunger. A change in phase of a hydrocarbon contained in a cylinder caused by temperature change, causes movement of the brass plunger. The units are available for various temperature ranges. The adaptation considered was to monitor the outlet water temperature from individual process tubes in the ``G`` pile. The purpose of the test was to determine the magnitude of error, if any, that is induced in a standard Vernatherm unit of known calibration when subjected to gamma irradiation. The accuracy of the units prior to irradiation was within 1.25 F. An examination of the calibration curves shows that a hysteresis effect in the hydrocarbon of the unit causes the curve of descending temperature to be displaced from the ascending temperature curve. The effects of irradiation were to decrease the accuracy to within 3.75 F. After a total exposure of 17,416 {times} 10{sup 4}R at 1.1 MEV. Since the exposure of 11,441 {times} 10{sup 4}R is equivalent to approximately 2,000 months exposure in the pile at 250 MW they can conclude that the effect of radiation is not detrimental since the increase in accuracy is only within 0.75 F.
Date: October 31, 1951
Creator: Smith, J. L.
Partner: UNT Libraries Government Documents Department

{open_quotes}O{close_quotes} ring sealed process tube, Phase II, test project

Description: The {open_quotes}O{close_quotes} ring seal has been proposed to replace the van stone flange and the bellows thermal expansion assembly currently used on the existing Hanford piles to achieve water and gas seals, respectively. Possible advantages of the {open_quotes}O{close_quotes} ring seal are: (1) simplification of component parts and elimination of van stone corrosion; (2) simplification of maintenance; (3) lower costs of initial erection; (4) increased strength. This test supplements Test Project No. 27 (a preliminary thermal cycling test) in applying the {open_quotes}O{close_quotes} ring seal assembly to actual pile operating conditions.
Date: April 9, 1951
Creator: Johnson, R. E.
Partner: UNT Libraries Government Documents Department

General Electric Company Hanford Works, Project C-431-A Production Facility-Section A, design report

Description: The 100-C project is to be located adjacent to the present 100-B Area. It is planned to build an addition to the present 181-B river pump house using the same elevations for pump settings, intakes, and floors as for the present pump house, thus maintaining the same suction conditions and flood protection as B Area. The 105 Building will be located on higher ground than B Area and therefore, protection against possible flood damage is assured. This report is divided into the following sections: (1) general description of project; (2) addition to existing river pump house; (3) raw water lines from 181-B addition to 183-C lead house; (4) the 183-C filter plant; (5) 190-C process pump house; (6) power house addition; (7) high tanks; (8) retention basins; (9) outside streamlines; (10) primary substation; (11) outside underground lines; (12) outside electric lines; (13) roads, railroads, walks, fences; (14) structural design of all buildings; and (15) architectural design of all buildings.
Date: March 29, 1951
Creator: Colburn, R. T.
Partner: UNT Libraries Government Documents Department