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Geophysical Seismic Evaluation Study at Hanford

Description: From introduction: "In June, 1963, a geophysical research program was conducted at Hanford to determine the feasibility and desirability of using seismic methods in geohydrologic studies. Detection and delineation were desired of seven different geological features that in some sites affect the movement of liquid radioactive wastes discharged to the ground."
Date: December 1964
Creator: Brown, Ruth E. & Raymond, John R.
Partner: UNT Libraries Government Documents Department
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Thermo-physics technical note No. 37: SNAP- 10A, Stainless Steel-316 vessel wall ablation. Final report

Description: The altitudes and times of ablation have been determined for the SNAP-10A, SS-316 vessel wall reentering under various conditions. The results are confined to one typical location on the reactor and to one typical reentry trajectory. The location is the side wall of the vessel and the trajectory is the one used in NAA-SR-8303.
Date: December 7, 1964
Creator: Montgomery, L.D.
Partner: UNT Libraries Government Documents Department
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Report on Carbon-14 generation and release at some of the Hanford reactors

Description: The Hanford graphite-moderated reactors have an enclosed gas circulation system to maintain control of the composition of gas atmosphere in the graphite stack. This investigation was undertaken to answer several questions concerning the generation and release of Carbon-14 in the operation of these graphite moderated reactors. The principle question was: Will an increase in the nitrogen content of the reactor atmosphere increase the release of Carbon-14 sufficiently to create a health hazard. Ot… more
Date: December 14, 1964
Creator: Barton, G.B.
Partner: UNT Libraries Government Documents Department
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Radioactive liquid waste disposal for October, 1964

Description: This report details what types and amounts of liquid wastes were disposed in the ground at Hanford in October, 1964.
Date: December 22, 1964
Creator: Wilson, R. H.
Partner: UNT Libraries Government Documents Department
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Effects of Hanford Operations on Columbia River temperatures: Interim report No. 2

Description: A research and development project for study of the effects of reactor effluent on Columbia River water quality is being sponsored by the AEC Division of Production. Work was started in October 1962, the first effort being aimed at furnishing an immediate answer to a security question: how closely can Hanford production be estimated by measurement of river temperatures? An interim progress report gave the results of the preliminary investigation. During the calendar year 1963, the study was exp… more
Date: December 3, 1964
Creator: Corley, J. P.
Partner: UNT Libraries Government Documents Department
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Hanford Laboratories monthly activities report, November 1964

Description: This is the monthly report for the Hanford Laboratories Operation, November 1964. Reactor fuels, chemistry, dosimetry, separation processes, reactor technology, financial activities, biology operation, and physics and instrumentation research.
Date: December 15, 1964
Partner: UNT Libraries Government Documents Department
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Top shield temperatures, C and K Reactors

Description: A modification program is now in progress at the C and K Reactors consisting of an extensive renovation of the graphite channels in the vertical safety rod ststems. The present VSR channels are being enlarged by a graphite coring operation and channel sleeves will be installed in the larger channels. One problem associated with the coring operation is the danger of damaging top thermal shield cooling tubes located close to the VSR channels to such an extent that these tubes will have to be remo… more
Date: December 28, 1964
Creator: Agar, J. D.
Partner: UNT Libraries Government Documents Department
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Production Test IP-725 increased graphite temperature limit: F Reactor

Description: The fundamental objective of the graphite temperature limit is to prevent excessive oxidation of the graphite moderator blocks with carbon dioxide and water vapor in the reactor atmosphere. Laboratory tests have shown that 10 percent uniform oxidation of graphite results in a loss in strength of approximately 50 per cent. This value of a strength loss of 50 percent has been arbitrarily established as the limit to graphite oxidation over the lifetime of the reactor stack. This limit has been fur… more
Date: December 1, 1964
Creator: Russell, A.
Partner: UNT Libraries Government Documents Department
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Research and Development Irradiation Processing Department semiannual report

Description: The 02 Research and Development program for the Irradiation Processing Department is contained in seven 189-forms, R-1 through R-6 and M-1 and M-2. The subprograms designated by R pertain to reactor research and development, and those designated by M pertain to the metallurgy or the fuels research and development. This report covers the progress in each of the subprograms on an individual basis and follows the format proposed by RLOO. Although the reports are brief, the results are presented in… more
Date: December 1, 1964
Creator: Greager, O. H.
Partner: UNT Libraries Government Documents Department
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Reactivity measurements of various target elements

Description: The amount of enriched uranium to support various type of target elements was determined in the Hanford Test Reactor. This report describes the measurement of separate and striped loadings for canned thorium oxide, bismuth, lithium-aluminum, and, in addition, bare depleted uranium. This experiment was undertaken to provide information needed to estimate the E-metal requirements in a production reactor when replacing natural uranium with target material. The amount of enriched uranium which is r… more
Date: December 1, 1964
Creator: Blyckert, W. A.
Partner: UNT Libraries Government Documents Department
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Carbon dioxide for pH adjustment 100-K Reactors

Description: This report presents the results of a recent analysis to determine if there is a practical method for using carbon dioxide for pH adjustment at the 100-K Reactors. Carbon dioxide could be recovered from the boiler stack gas and introduced into the K Reactor process water. The approximately $240,000 installation cost would be repaid in about one year by the reduction of sulfuric acid costs. The proposed system would consist of a blower, a purification system, and a distribution system for conduc… more
Date: December 15, 1964
Creator: Young, J. R.
Partner: UNT Libraries Government Documents Department
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Reactivity balance and associated reactor physics data, November 1964

Description: Data in this report are significant to Pile Physics calculations and are submitted by the Area Physicists at the respective reactors. Reactivity in non-uranium charges and in radial and spike enrichment is calculated either by one-group diffusion theory or by the simpler flux-squared weighting method. The former method provides a more accurate evaluation for larger enrichment inventories; the latter method is sufficient for radial enrichment of less than about 0.25 percent excess K.
Date: December 4, 1964
Creator: Clark, D. E.
Partner: UNT Libraries Government Documents Department
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Investigation of terminal corrosion rates in aluminum process tubes: Interim report, PT-IP-674

Description: Each of the 25 monitor tubes at B and D reactors have been gauged four to six times since they were installed in late 1961 or early 1962. Since October, 1962, the WTG data indicates the average corrosion rate, is 0.25 to 0.30 mils per month. The corrosion rate of the thinnest tube is about the same as the average tube. As expected, the corrosion rate is low and believed to be a measure of top-wall corrosion. It is estimated that it will take approximately one more year (at 6.6 pH) before the bo… more
Date: December 15, 1964
Creator: Hough, C. G.
Partner: UNT Libraries Government Documents Department
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KER-3 operating report, Test K-3-18, PT IP-645

Description: The purpose of this test was to demonstrate and characterize the simultaneous generation of plutonium and tritium. The data charged was February 10, 1964 at 12:00 noon. The fuel elements were thirteen 26.1 inch co-product test assemblies. The fuel was exposed for a total of 2,828 hours and at run conditions for 2,288 hours. The date discharged was June 7, 1964. Goal exposure was met.
Date: December 23, 1964
Creator: Quinn, H. T.
Partner: UNT Libraries Government Documents Department
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Tentative U-233 and thorium nitrate specifications

Description: This report discusses the review of the proposed thorium nitrate specifications,the preparation of tentative product specifications for Purex U-233 and thorium nitrates, and an estimation of the feasibility, cost and product composition for providing U-233 oxide at Hanford. The tentative specifications proposed for U-233 and thorium product for the Purex Plant are presented. The values chosen represent the understanding of feed material and reactor processing needs and the current estimates of … more
Date: December 18, 1964
Creator: Tomlinson, R. E.
Partner: UNT Libraries Government Documents Department
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Report to the Working Committee of the Fuel Element Development Committee from the General Electric Company, Hanford

Description: Discussed topics on current reactor production fuels include: uranium core production data, uranium specifications, induction heat treating, fuel performance, residual stress measurements, AlSi process development, thoria program, and self-support program. The N-reactor fuels production is discussed. And concerning N-Reactor fuels development, process development and irradiation experience are discussed.
Date: December 29, 1964
Creator: Minor, J. E.; Lewis, M. & Stringer, J. T.
Partner: UNT Libraries Government Documents Department
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KER-1 operating report: Test K-1-23 PT IP-601 and PT IP-601, Supplements A and B

Description: For the test detailed in this report, the charge consisted of three NIEL fuel elements, two lithium-aluminum target elements, and front and rear crud probe train assemblies containing four ceramic fueled crud probes as authorized by PT IP-601. The objectives of these tests were to evaluate the crud forming characteristics of loop coolant containing ammonium hydroxide for pH control by operating at conditions generally regarded to induce high crud concentrations and to provide lithium-aluminum s… more
Date: December 23, 1964
Creator: Dallas, H. A.
Partner: UNT Libraries Government Documents Department
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Design test request No. 1263 K Reactor graphite key and VSR channel sleeve test

Description: The objectives of this test were: (1) Determine the coefficient of friction between two adjacent layers of K Reactor graphite at room temperature. (2) Determine the average load required to cause failure of an unirradiated K Reactor side reflector bar, when subjected to tensile loading applied through the reflector keys. (3) Determine the average load at failure and the average deflection at failure of a single VSR channel key when loaded in keyways with clearances equal to those used in origin… more
Date: December 10, 1964
Creator: Kempf, F. J.
Partner: UNT Libraries Government Documents Department
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Test Request LTFY-2

Description: This test request defines pre-test data for the irradiation of enriched yttrium-uranium hydride samples in the LITR C-48 facility.
Date: December 1, 1964
Partner: UNT Libraries Government Documents Department
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Chemical Processing Department Monthly Report: November 1964

Description: This report for November 1964, from the Chemical Processing Department at HAPO, discusses the following: Production operation; Purex and Redox operation; Finished products operation; maintenance; Financial operations; facilities engineering; research; employee relations; and weapons manufacturing operation.
Date: December 21, 1964
Creator: Hanford Atomic Products Operation. Chemical Processing Department.
Partner: UNT Libraries Government Documents Department
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