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Evaluation of Diethers as Uranium Extractants

Description: Report on the determination of several physical properties, pertinent to uranium extraction, for a number of ethers and related compounds.
Date: January 14, 1963
Creator: Googin, J. M.; Harper, W. L.; Phillips, L. R. & Postma, Fred W.
Partner: UNT Libraries Government Documents Department
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Two-Facility Approach to Investigations of Fast Reactor Meltdowns

Description: Report issued by the APDA over studies conducted on hypothetical fast reactor meltdown accidents. As stated in the summary, "the purpose of this study is to investigate the technical feasibility of conducting fast reactor meltdown experiments to determine a more realistic maximum accident and to provide a better evaluation of fast reactor safety" (p. 7). This report includes tables, and illustrations.
Date: January 15, 1963
Creator: Doyle, T. A.; Page, E. M.; Nicholson, R. B.; Hagstrom, J. T. & Nims, J. B.
Partner: UNT Libraries Government Documents Department
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Electrostatic Classification of Submicron Airborne Particles : Final Report, August 16, 1961 to January 31, 1963

Description: From abstract: "This project was a study of electrostatic classification of submicron aerosols. Classification of particles as small as 0.006-[mu]-diameter was shown to be feasible, and good classification of atmospheric dust was achieved. However, a practical solution to the problem of overlapping between particles larger and smaller than 0.1 [mu], the point of minimum electric mobility, was not found."
Date: January 31, 1963
Creator: Langer, G.
Partner: UNT Libraries Government Documents Department
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Savannah River Plant 200 Area technical manual. Part SP. Processing of Np/sup 237/ and Pu/sup 238/

Description: This manual covers the technology involved in the 200 Area process for the recovery of Np/sup 237/ from certain aqueous waste streams in the separations plants, for the recovery of NP/sup 237/ and Pu/sup 238/ from irradiated NpO/sub 2/-Al slugs and for the fabrication of NpO/sub 2/-Al slugs. The manual contains sections on the fundamental chemistry, the primary recovery of Np by ion exchange, the decontamination of Np by ion exchange, the processing of NpO/sub 2/-Al targets, the separation and … more
Date: January 3, 1963
Creator: Hill, A.J. (comp.)
Partner: UNT Libraries Government Documents Department
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Proposed Redox sand filter monitor and stack monitors

Description: The purpose of this January, 1963 report is to review existing Redox exhaust gas sampling equipment and to propose modifications and additions where appropriate. A study was conducted to determine what modifications, if any, should be made to the Redox exhaust gas sampling equipment to improve their present methods of monitoring for excessive amounts of fission product activity.
Date: January 15, 1963
Creator: Oliver, R. G.
Partner: UNT Libraries Government Documents Department
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Post-irradiation data on fuel elements from KER Loop 4

Description: Fourteen NAE1 fuel elements were discharged from KER Loop-4, after irradiation to an average exposure of 1250 MWD, at prototype N-Reactor coolant temperature and pressure. The elements were disassembled and measured in the KE fuel examination facility. This report includes all measurements, except the profilometer data.
Date: January 10, 1963
Creator: Bennett, E. C.
Partner: UNT Libraries Government Documents Department
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Report to the working committee from the General Electric Company, HAPO

Description: Information is presented on current reactor fuel development (uranium core production data, fuel performance, AlSi process development, and alternate process development) and NPR fuel development (fuel production status, KER loop testing, and process development).
Date: January 7, 1963
Creator: Stringer, J. T. & Minor, J. E.
Partner: UNT Libraries Government Documents Department
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Draft of physics sections to 100-N technical manual

Description: The information presented is a collection of most of the physics information available for the New Production Reactor. The details of some of the physics information, particularly those dealing with exposure and temperature effects, are by no means to be considered the final word since there has been no experimental verification of these effects. However, the gross physics characteristics described are felt to be reasonable representations of the expected physics behavior of N Reactor and shoul… more
Date: January 25, 1963
Creator: Nilson, R.
Partner: UNT Libraries Government Documents Department
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Report of invention

Description: This invention discloses a method of making a synthetic nuclear fuel by mixing pure U-233 with U-238 fuels, such as depleted uranium, to produce a fuel that combines the most desirable nuclear properties of both the U-233 and U-238 fertile material. The process requires that U-233 be manufactured in such a manner as to be relatively uncontaminated from U-232. The subject of this invention is a method of fuel handling that incorporates the desirable features of both U-233 and U-238. It is propos… more
Date: January 23, 1963
Creator: Lang, L. W.
Partner: UNT Libraries Government Documents Department
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Loading, operating conditions, and water shutoff times for a charge of twelve 17-inch N inner fuel tubes or twelve 18-inch U-2 w/o Zr elements, PT-IP-536-A and PT-IP-536-A, Supplement B

Description: Production test IP-536-A authorizes the irradiation of N Reactor inner fuel tubes in KER-1 and KER-2. Supplement B, PT-IP-536-A, authorizes the irradiation of N Reactor inner fuel tubes prepared from a U-2 w/o Zr alloy. Both tests require that specific operating conditions and trip settings for particular loadings be approved by the managers of the Process and Reactor Development Sub-Section and the Process Technology Sub-Section prior to charging. The purpose of this document is to provide the… more
Date: January 28, 1963
Creator: Kratzer, W. K. & Wise, M. J.
Partner: UNT Libraries Government Documents Department
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Contraction of graphite: A comparison of laboratory and production reactor data, Part 2, KE and KW Reactors

Description: Part 1 of this two-part report presented a comparison of the irradiation-induced contraction rates obtained on standard-size graphite samples and the apparent moderator contraction rates of H, DR and C Reactors. The distortion trends of the top center of the graphite stacks, from which the apparent moderator contraction rates were derived, were presented as a function of cumulative power generation since start-up for each of the six older Hanford reactors. Since KE and KW Reactors are of identi… more
Date: January 2, 1963
Creator: Giberson, R. C. & Morgan, W. C.
Partner: UNT Libraries Government Documents Department
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Distribution of time between unscheduled outages

Description: A study is in progress in which reactor operations will be simulated on the computer, the primary purpose being to evaluate the costs associated with various administrative alternatives which may be followed in conducting the overall operation, in addition to defining how operational costs are affected by such things as changes in fuel quality. The problem is complicated by the fact that the operation of the reactors is largely affected by random occurrences; no one can predict exactly when a t… more
Date: January 2, 1963
Creator: Jaech, J. L. & Burke, R. C.
Partner: UNT Libraries Government Documents Department
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Status of alloyed dingot program, January 1963

Description: This report summarizes and highlights the more importan milestones, development programs, performance and characteristics, and properties of dingot uranium and its use in the Hanford reactors from 1955 to the present. For the benefit of those unfamiliar with the terms ingot and dingot uranium as used in this report, ingot uranium refers to the metal made at the Fernald Plant of the National Lead Company by remelting under vacuum a mixed charge of solid scrap, briquetted scrap, and derby metal (… more
Date: January 11, 1963
Creator: Weakley, E. A.
Partner: UNT Libraries Government Documents Department
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Purex process performance summary, January 1963 thru December 1963

Description: This report documents information acquired from the operation of the purex process during the year of 1963 at the Hanford Site. The report is broken down into sections containing data collected on two to four week intervals. The data included: Performance, flowsheets, feed preparation, solvent extraction, product treatment, solvent treatment, acid recovery, waste concentration, fission product recovery, and waste treatment and storage.
Date: January 15, 1963
Creator: Judson, B. F.
Partner: UNT Libraries Government Documents Department
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Metastability of alpha plutonium

Description: The metastability of alpha plutonium above the {alpha} {r_equilibrium} {beta} equilibrim transformation temperature (112 C) was studied by metallographic techniques. The purpose of this study was to extend the previous work on the {alpha} {yields} {beta} transformation which was accomplished using fluid displacement techniques{sup 1} and to obtain a basis for determining the length of time the alpha phase is stable at high temperatures. Approximate isothermal reaction curves were determined exp… more
Date: January 21, 1963
Creator: Nelson, R. D.
Partner: UNT Libraries Government Documents Department
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Critical mass control specification 7.35 weight percent Pu-A1 alloy fuel element storage gas cylinder storage area, 234-5 building

Description: Plutonium-aluminum fuel elements, which were fabricated at Hanford Atomic Products Operation for a special Atomic Energy Commission program, but were rejected for failure to meet specifications, were returned to Hanford for recovery. These elements, although contaminated during acceptance checking have not been used in the proposed reactor tests. This special material will be stored until recovery is completed. This report provides the critical mass control specification for the 7.35 weight per… more
Date: January 16, 1963
Creator: Sloat, R. J.
Partner: UNT Libraries Government Documents Department
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Radiolysis of Organic Fluids, Annual Progress Report: October 1, 1961-September 30, 1962

Description: From introduction: This report reviews the Susie program (particularly reactor dosimetry and data analysis) as well as other items that represent a smaller share of the total effort.
Date: January 15, 1963
Creator: Bolt, R. O.; Burrous, M. L.; Carroll, J. G.; Hall, K. L.; Sweeney, M. A. & Tobriner, M. W.
Partner: UNT Libraries Government Documents Department
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Warp failure of a thirty-six inch long uranium 2 wt % zirconium alloy tubular fuel element, PT-IP-250-A (RM-568). Final report

Description: The N-Reactor will be charged with tubular fuel elements consisting of two components. Both components, an outer tube with a concentric inner tube, have a uranium core, coextruded with a Zircaloy-2 cladding. The testing in support of N-Reactor fuels has been conducted in the experimental loops in the K-East Reactor. Although the process tubes in the KER loops are smaller than the proposed N-Reactor process tubes, the test loops operate at the water temperatures and pressures that will exist in … more
Date: January 25, 1963
Creator: Kuhlken, L. E.
Partner: UNT Libraries Government Documents Department
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