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LITHIUM HYDRIDE PROPERTIES

Description: A tabulation is presented of values for selected properties of lithium hydride. (M.C.G.)
Date: March 14, 1961
Creator: Welch, F.H.
Partner: UNT Libraries Government Documents Department
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REMOTE DISSOLUTION AND ANALYTICAL PROGRAM FOR IRRADIATED THORIUM

Description: A remote dissolution and analytical program for irradiated thorium is given. The aluminum jacket on the slug was dissolved with 6M nitric acid and 0.005M mercuric nitrate. After a water wash, the thorium dissolution was accomplished with concentrated nitric acid made 0.04M in hydrofluoric acid. Weighing, dissolving, and sampling were done remotely in the multicurie cell at the Idaho Chemical Processing Plant. Handling techniques for weighing and dissolving the slugs are described. Transferring … more
Date: July 14, 1961
Creator: Huff, G. A.; Doggett, I. L.; Fletcher, R. D. & Jacobson, M. E.
Partner: UNT Libraries Government Documents Department
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An Integral Design Technique for Wideband Multistage Transistor Amplifiers

Description: A philosophy for designing wideband multistage transistor amplifiers is presented. The amplifier was visualized as an integral unit, the interstage networks constituting the elements of the amplifier unit. By designing the amplifier as a unit and adjusting the over-all response (gain and bandwidth) with the interstage time constants, an increase in gain-bandwidth product was realized over the iteratively designed amplifiers. The resulting increase in gainbandwidth product resulted from absence … more
Date: December 14, 1961
Creator: Scott, L.
Partner: UNT Libraries Government Documents Department
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Literature Survey on World Isotope and Radiation Technology : First Interim Report Covering the Period from June 15, 1961 to August 14, 1961

Description: Abstract: "This is the first interim report of a literature survey investigating the uses and technology of radioscopes in the countries of the world, with particular emphasis necessarily placed on those more highly industrialized nations. Part I includes a general summary of the quantity and quality of radioisotope work being performed in these countries. Among the outstanding radioisotope applications with respect to quantity is the work of Japan in chemical research, that of USSR in metals r… more
Date: August 14, 1961
Creator: Haffner, J. W. & Stone, C. A.
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
Partner: UNT Libraries Government Documents Department
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Irradiation Processing Department Monthly Report: July 1961

Description: This document details activities of the irradiation processing department during the month of July 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: August 14, 1961
Creator: Hanford Atomic Products Operation. Irradiation Processing Department.
Partner: UNT Libraries Government Documents Department
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Measurement procedures for purified birch

Description: Since start-up of the neptunium recovery and purification program at HAPO, the neptunium-has been subjected to the following process steps: Production of crude neptunium nitrate by the Redox and Purex plants; Production of purified neptunium nitrate, using an anion exchange process, in research and development facilities operated by CPD`s Process Chemistry Operation; Production of neptunium oxide (NpO{sub 2}) by Process Chemistry. Mixing the NpO{sub 2} powder with aluminum powder and incorporat… more
Date: August 14, 1961
Creator: Buckingham, J. S.
Partner: UNT Libraries Government Documents Department
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Process improvement transition authorization IP-17-AI, reduction of the amount of dichromate added to process water

Description: This PITA is designed to permit large-scale application of a change in process water inhibitor concentration before a permanent change to the Water Plant -- Process Standards is fully justified and implemented. Specifically, this PITA authorizes reducing process water dichromate concentration to 1.0 ppm at all reactors (C excluded), provided pH remains at 7.0 {plus_minus} .1.
Date: July 14, 1961
Creator: Nesselson, E. J. & Shimer, R. D.
Partner: UNT Libraries Government Documents Department
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Analog program in reactor speed of control studies

Description: One of the characteristics of the safety control system of the Hanford reactors which is of primary concern from the standpoint of reactor safety is the response time. The purpose of this study is to determine whether the safety control system is sufficiently fast-acting to prevent an intolerably large power excursion from developing. An intolerably large power excursion is one that would cause a melting of the uranium while the reactor power is above the previous operating level. The purpose o… more
Date: June 14, 1961
Creator: Cameron, W. D. & Tiller, R. E.
Partner: UNT Libraries Government Documents Department
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Analysis of radiation induced stresses in C Reactor graphite

Description: Figures are included which gives the necessary information on C Reactor for analysis of stress buildup in the graphite tube blocks.
Date: August 14, 1961
Creator: Yoshikawa, H. H.
Partner: UNT Libraries Government Documents Department
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Fuels Development Operation quarterly progress report, January--March 1961

Description: The present Quarterly Report is the continuation of a series issued by the new Fuels Development Operation. Reports in this series combine portions of the quarterly reports by the former Metallurgy Research and Fuel Technology Sub-Sections. Work reported includes research conducted by the Physical Metallurgy Operation, and research and development conducted by Fuel Design, Fuels Fabrication Development and Ceramic Fuels Development Operations.
Date: April 14, 1961
Partner: UNT Libraries Government Documents Department
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TOE work sheets

Description: This report provides operational worksheets detailing charge/discharge, maintenance, fuel element ruptures, leaks, tube replacements, and production data.
Date: September 14, 1961
Creator: Chatten, J. C. L.
Partner: UNT Libraries Government Documents Department
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Production yield data as a function of graphite temperature

Description: This report consists of eight curves, showing Plutonium-240 concentration and conversion ratio as a function of graphite temperature for various goal exposures. A range of 450 to 1000 degrees centigrade on the moderator temperature is used. Other parameters are consistent with the methods and constants used in present product accountability. No attempt has been made to state absolute conversion ratios or Pu-240 percentages. The purpose of this report is to provide a basis for use in economic st… more
Date: June 14, 1961
Creator: Montague, D. G.
Partner: UNT Libraries Government Documents Department
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A Reliability Improvement Program Planning Report for the SNAP 10A Space Nuclear Power Unit

Description: The estimated achieved reliability of SNAP 10A space nuclear power units will be relatively low at the timeof the first SNAPSHOT flight test in April 1963 and the existing R&D program does not provide a significant reliabiity growth thereafter. The total costs of an 8-satellite network using SNAP 10A units over a 5-year period has been approximated for the case where the total cost of a single satellite launched is 8 million dollars.
Date: March 14, 1961
Creator: Coombs, M. G.; Smith, C. K. & Wilson, L. A.
Partner: UNT Libraries Government Documents Department
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Radioactive contamination in liquid wastes discharged to ground at separations facilities through December 1960

Description: This document summarizes the amounts of radioactive contamination discharged to ground from separations facilities through December 1960. Detailed data for individual disposal sites are presented on a month-to-month basis for the period of July through December 1960.
Date: April 14, 1961
Creator: Henle, R. C.
Partner: UNT Libraries Government Documents Department
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Measurements of radioisotopes and trace constituents in the PRTR D{sub 2}O and helium systems

Description: During the first two weeks of May while PRTR was being tested at a power level of a few MW, rather large amounts of some fission product gases were observed in the helium system. Samples of D{sub 2}O from the primary cooling system taken during the second week of May were analyzed and found to contain I{sup 131-133-135} and some fission gases (and their daughters) but practically no other fission products. On May 14 the reactor power level was raised to 10 MW and operated at about that level un… more
Date: June 14, 1961
Creator: Perkins, R. W. & Thomas, C. W.
Partner: UNT Libraries Government Documents Department
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PERIODIC CALIBRATION OF TEMPERATURE SENSING ELEMENTS. CORE I, SEED 2. Test Results (T-641303-B)

Description: Tests were conducted to determine the direction and magnitude of any short- or long-term drift in core thermocouples, primary loop and pressurizer resistance thermometers, and resistance thermometers located in the secondary side of the boilers for Seed 2 at 2303 EFPH. It was found that drift in the core thermocouples is definite but random. Other findings are discussed and calibration data are presented graphically. (J.R.D.)
Date: April 14, 1961
Partner: UNT Libraries Government Documents Department
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Valve Operating System Performance Test. Core 1, Seed 2. Test Results T- 641114

Description: A test was run on the Shippingport Pressurized Water Reactor on June 15, 1960, to determine whether or not the pressure snd water flask volume of the valve operating system are sufficient to meet requirements under both normal and emergency conditions. The system was found to be satisfactory. A two-hour leak test indicated leakage. (D.L.C.)
Date: March 14, 1961
Partner: UNT Libraries Government Documents Department
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A Survey of the Hazards Involved in Processing Liquid Metal Bonded Fuels

Description: A survey of the character and magnitude of hazards involved in processing liquid metal bonded fuels was made and the scope of a preliminary experimental program outlined. Processing of SRE and CPPD fuels by mechanical decladding followed by controlled reaction of the collected methods. Simdlarly, shearing of PRDC fuel and controlled exposure of the Na in the severed portions to water appears more desfrable than chethical dissolution of the metallic cladding. (auth)
Date: August 14, 1961
Creator: Adams, J. B.
Partner: UNT Libraries Government Documents Department
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EGCR Core Structural Analysis. The Effects of Fast-Neutron Irradiation and the Bowing Characteristics of the Graphite Columns

Description: An analysis of the EGCR core structure was made to determine the lateral deflections (bowing) of the graphite columns resulting from shrinkage caused by fast-neutron irradiation, the life expectancy of each column due to restraints imposed on the bowing, and the reaction forces induced in the supporting structures. Based on currently avallable data for EGCR type graphite shrinkage and assuming experimental loop operation, a maximum bowing potential of 3.61 in. was calculated for an interior col… more
Date: April 14, 1961
Creator: Moore, S. E. & Shaw, W. A.
Partner: UNT Libraries Government Documents Department
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Corrosion of Alloys in Various ICPP Decontamination Solutions

Description: Corrosion studies were conducted on stainless steel types 347 and Carpenter-20, Monel, titanium 55A, and tsntalum in decontamination solutions. These solutions are: 10% nitric acid, 10% citric acid, 10% sodium hydroxide--2.5% tartaric acid, 10% oxalic acid, 0.003M periodic acid in 0.05M nitric acid, 3% sodium fluoride --20% nitric acid, Turco 4501 and Turco 4502, and 0.25M phosphoric acid. Boron stainless steel type 304L was studied in 10% sodium hydroxide--2.5% tartaric acid, 10 and 60% nitric… more
Date: April 14, 1961
Creator: Hoffman, T. L. & Adams, G. S.
Partner: UNT Libraries Government Documents Department
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Aqueous Processes for Dissolution of Uranium-Molybdenum Alloy Reactor Fuel Elements

Description: Methods for dissolving unirradiated uranium-molybdenum alloy reactcr fuels in nitric acid, nitric acid--ferric nitrate, and nitric acid-- phosphoric acid solutions were studied on a laboratory scale. Flowsheets based on the results propose dissolution of alloys containing 3% molybdenum in boiling 6 M HNO/ sub 3/ to yield stsble solutions that are 0.6 M in uranium and 3 to 4 M in nitric acid. The uranium can then be easily decontaminated and recovered in a conventional Purex-type tributyl phosph… more
Date: July 14, 1961
Creator: Ferris, L. M.
Partner: UNT Libraries Government Documents Department
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Periodic Intercalibration of Temperature Sensing Elements. Core I, Seed 2. Test Results (T-641303)

Description: Tests were conducted to determine the direction and magnitude of drift in core thermocouples, primary loop and pressurizer resistance thermometers, and the resistance thermometers in the secondary side of the boilers. The temperature sensing elements of the reactor coolant loops did not show any significant short-term error. The tests of the core thermocouples were not conclusive. Test data are included. (J.R.D.)
Date: March 14, 1961
Partner: UNT Libraries Government Documents Department
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