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Pile graphite expansion

Description: The purpose of this memorandum is to present and analyze, in terms of the current status of knowledge of radiation damage to graphite, the data available at the present time on the expansion status of the graphite in the piles, and suggest, in terms of this analysis, several possibly feasible curative and preventive measures. The portion of the data to be covered in this memorandum consists of that obtained during the last four years from pile motion measurements and from tube bowing measuremen… more
Date: July 24, 1950
Creator: Warekois, E. P. & Reinker, P. H.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Final report on Process Test MR-105-2, Orifice selection during reactor operation

Description: The test established that a practical orifice selecting device can be made and used to control the water flow rate to a process tube at either of two accurately calibrated rates with no loss of accuracy in flow measurement. With the selector tested, there was no flow restriction during the orifice transition. The pressure fluctuations during the change were small in magnitude, and caused no operational problem. The test demonstrated that orifice selection is feasible from operating other factor… more
Date: September 15, 1952
Creator: Schilling, R. D.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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In-reactor corrosion of X-8001 and 1245 aluminum: Analysis of data from PT IP-42A

Description: Failures of standard fuel element jackets (1245 aluminum alloy) after relatively short Hanford reactor exposures are occurring at high reactor power levels. Metallographic examination of fuel element jackets from short exposure ruptures shows the cause of failure to be rapid intergranular corrosion. This type of attack has been reproduced in laboratory tests by exposure to water at temperatures above 200 C, or to steam at temperatures higher than 300 C. Flow disruptions due to misalignment of t… more
Date: June 25, 1958
Creator: Dillon, R. L. & Richman, R. B.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Machining & installation of graphite for 105 DR & H

Description: This report describes the basic design, intermediate and final stacking procedures, and graphite behavior of nuclear reactors DR and H during construction. Included in the report are test records to substantiate basic design assumptions and data and the actual performance of the graphite during preliminary and final stacking.
Date: October 1, 1949
Creator: MoKenna, W. R.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Appendix to HDC 2118 design criteria 100-X reactor water plant, general description - section II

Description: The factors responsible for the advances of 100-X compared with the older areas are: Simplification of the process, such as elimination of separate process water clearwells, by having the filtered water reservoirs perform that function. Combination of separate buildings into one building, such as combining filter pump house and process pump house. Use of electric standby. Use of higher capacity pumps and filter basins, and so fewer number of units. Centralization of control and operation. More … more
Date: March 29, 1952
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Pile Temperature Study

Description: Regarding heat transfer studies of annular spaces around the process tube, there is general agreement among all concerned, that high graphite temperatures are essential at the initial startup. Pile Technology, in studying graphite damage, has developed information that shows little or no expansion occurring when temperatures are maintained at 275{degrees}C. Stored energy levels are less than 5% and K/Ko has saturated in the region of 3.5 to 4. Badly expanded samples (1% increase in length) have… more
Date: January 17, 1950
Creator: Jaske, R. T.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Hanford Laboratories Operation Monthly Activities Report: January 1961

Description: This is the monthly report for the Hanford Laboratories Operation, January 1961. Metallurgy, reactor fuels, chemistry, dosimetry, separation processes, reactor technology, financial activities, visits, biology operation, physics and instrumentation research, and employee relations are discussed.
Date: February 15, 1961
Creator: Hanford Laboratories
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Production Test IP-719: The effect of water plant variables on effluent activity. Final report

Description: One source of the parent materials which are converted into the radioisotopes in reactor effluent is the impurity content of Columbia River water. It has been demonstrated that as the efficiency of removal of the radioisotope parent materials increases, the amount of radioisotopes in the reactor effluent decreases. An example of this is the activity reduction which results from the use of high alum feed. In order to determine whether effluent activity would be influenced by the length of filter… more
Date: February 23, 1965
Creator: Geier, R. G.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Irradiation Processing Department monthly report, March 1961

Description: This document details activities of the irradiation processing department during the month of March, 1961. A general summary is included at the start of the report, after which the report is divided into the following sections: Research and Engineering Operations; Production and Reactor Operations; Facilities Engineering Operation; Employee Relations Operation; Financial Operation; and NPR project.
Date: April 14, 1961
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Interim report, cocked-slug, flush-charging relations for C-Pile conditions

Description: Pile Engineering Sub-Section has been investigating the causes and effects of cocked slugs in process tubes for the past year because they are suspected to be the cause for some slug ruptures. In Project CG-642 - Continuous Charge-Discharge Equipment - C Reactor it is proposed that slugs be flush charged into the process tubes. This document reports the effect of flush charging slugs on their tendency to cock as discovered in laboratory tests.
Date: June 29, 1956
Creator: McCarthy, P. B.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Report on decreasing available acceleration of 190-B process pump turbines in order to reduce emergency steam demand

Description: As originally installed, the primary process pump turbines in 190-B were arranged to accelerate considerably upon loss of BPA electric power supply to the Process Pump House. However, the acceleration comes too late to be of value in maintaining top of riser pressure within the first second or two, and the acceleration results only in maintaining final process water pressure and flow at values higher than needed. It is desired to limit the acceleration of the turbines to a relatively small amou… more
Date: December 28, 1951
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Final report on Production Test 105-58-P -- B Pile reactivity under shutdown conditions

Description: Following the shutdown of the B Pile in March 1946 a method was devised for monitoring the sub-critical reactivity such that any significant change in neutron flux would be detected. This report summarizes the status of the unit until its start up in July 1948.
Date: July 19, 1948
Creator: Kruesi, F. E.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Final report on Production Test No. 105-1-MR -- Poison column control during reactor operation

Description: The lack of control rod capacity in the reactors with nine rods is causing significant production losses. The present control system, which functioned satisfactorily at a 300 MW equilibrium power level, is unable to counteract the larger startup reactivity transient effects at the current high power levels. This lack of strength causes the power level to be restricted during startup. The control system is also not flexible enough to prevent outages for the discharge of temporary poison. (1) A m… more
Date: July 24, 1952
Creator: Schilling, R. D. & Hess, K. W.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Hanford Engineer Works technical progress letter No. 134, January 19--25, [1947]

Description: This technical progress letter contains reports from six Technical Department divisions at the Hanford Engineer Works for January 19 through January 25, 1947. The six reporting divisions are: 100 Areas, 300 Area, 200 Areas, Chemical Development, Laboratories, and Statistical Studies. (JL)
Date: January 30, 1947
Creator: Greninger, A. B.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Hydrofluosilicic acid as a cap and can etchant

Description: Aluminum caps and cans are thoroughly cleaned, before being used to can slugs, to insure wetting of the metal surfaces by molten AlSi in the canning pot. An acid bath is used, as part of the cleaning operations to remove surface oxide and other surface films from the metal. Two acid solutions are authorized in the standard operating procedure; a 20% phosphoric acid solution for etching both caps and cans, and a 1% hydrofluosilicic acid solution to be used for caps only. It is desired to determi… more
Date: March 17, 1953
Creator: Dixon, D. S.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Investigation of KW reactor incident

Description: 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 c… more
Date: February 11, 1955
Creator: Sturges, D. G.; Hauff, T. W. & Greager, O. H.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Status of irradiations performed by testing and irradiation services for BNW as of August 18, 1968

Description: This report itemizes the irradiations performed by Testing and Irradiation Services for Battelle-Northwest. It lists the material being irradiated, awaiting disposition and material shipped during the report period. Data are given in table form. An explanation of the various columns in the report is given.
Date: September 9, 1968
Creator: Barker, L. V.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Production Test No. 105-522-E, Examination of pile process tubes

Description: The objective of the production test described in this report is to provide the authority and mechanism to remove process tubes from the piles for inspection. The test is intended to provide a more positive tube inspection program than was previously provided under production test number 105-9-P, ``Corrosion of Slugs and Tubes``, document number 7-3928.
Date: May 25, 1953
Creator: Falkoski, R. E.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Operating limits Hanford Production Reactors. Revision 2

Description: This report is applicable to the eight operating production reactors, B, C, D, DR, F, H, KE, and KW. It covers the following: operating parameter limitations; reactivity limitations; control and safety systems; reactor fuel loading; coolant requirements with irradiated fuel in reactor; reactor confinement; test facilities; code compliance; safety instrumentation and set points; and control criteria. Also discussed are administrative procedures for process control, training, audits and inspectio… more
Date: May 20, 1963
Creator: Owsley, G. F.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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