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909B high energy gull generator

Description: No Description Available.
Date: December 31, 1960
Creator: Stephens, W. H.
Partner: UNT Libraries Government Documents Department
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DMM: A Multigroup, Multiregion, One-Space-Dimensional Computer Program Using Neutron Diffusion Theory. Part 1 - The Theory

Description: DMM is a program using one-space-dimensional multigroup diffusion theory to calculate the reactivity or critical conditions and flux distribution of a multiregion reactor. Calculations of fission-produced xenon and samarium and time variation due to production and depletion of isotopes are an essential part of this program. The adjoint fluxes may also be computed, and the program includes the calculation of the nuclear constaants from fairly simple input combined with a library of cross sections. The present code is written for the Remington Rand 1103A. Operating instructions are presented in Part II. (auth)
Date: December 31, 1960
Creator: Leshan, Edward J. & Kavanagh, Deveroux L.
Partner: UNT Libraries Government Documents Department
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DMM: A MULTIGROUP, MULTIREGION ONE-SPACE-DIMENSIONAL COMPUTER PROGRAM USING NEUTRON DIFFUSION THEORY. PART II. DMM PROGRAM DESCRIPTION

Description: Operating instructions are presented for DMM, a Remington Rand 1103A program using one-space-dimensional multigroup diffusion theory to calculate the reactivity or critical conditions and flux distribution of a multiregion reactor. Complete descriptions of the routines and problem input and output specifications are also included. (D.L.C.)
Date: December 31, 1960
Creator: Kavanagh, D.L.; Antchagno, M.J. & Egawa, E.K.
Partner: UNT Libraries Government Documents Department
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[Hanford weekly teletype report]: Supplement report for week ending June 12

Description: This document contains information about flooding of the Columbia River. It focuses attention on the following; increased elevation due to rainfall, seepage which destabilized the constructed dike, flooding of cellars, evacuation of people to emergency shelters, tug boat collision damage to power lines, and the washout of the Van Giesen Street Bridge on Yakima River.
Date: December 31, 1960
Partner: UNT Libraries Government Documents Department
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ARMY GAS-COOLED REACTOR SYSTEMS PROGRAM SUMMARY REPORT ON MATERIALS FOR THE GCRE-II

Description: Investigatiors were made of various materials for development of metal- canned and semi-homogeneous GCRE-II fuel element concepts. The materials were studied for application to development of fuels, grapanite, silicon-silicon carbide coatings, metal claddings, carburization barrier coatings, and graphite joining. A survey of the literature showad that uranium carbide fuels are superior to other types for the applications described and that refractory metal or metal carbide fuel coatings appear superior to other types for use with the types of graphite investigated. Experimental measurements were made of the thermal conductivity, tensile strength, stress-strain reiationships, and thermal expansion of graphite powdsr bonded with baked carbon at a final firing temperature of 760 deg C. Results showed that these materials were stronger and more isotropic at all test temperatures than a standard structure graphite such as ATJ. The thermal conductivity is somewhat lower and the thermal extansion slightly higher than the corresponding properties of ATJ. A silicon-silicon carbide coating was developed as an osidation-resistant coating for graphite. Preliminary air oxidation tests at 1000 deg C showed that the first samples survived 2000 hr with 10% failure. Subsequent experiments showed that it is reasonable to expect better performance in further tests. Tests for compatibility with graphite were conducted on zirconium, Zircaloy-2, "A" nickel, and K-Monel at 1750 and 1850 deg F for 1000 and 1500 hr. Chemical analyses, metallography, and tensile tests indicated that the K-Monel is the material most compatible with graphite; it possesses good strength and ductility with negligible carburization or carbon diffusion. Zircaloy-2 tubing showed a growth of from 3.4 to 3.8% when thermal cycled 100 times between 850 and 1850 deg F. Tests for compatibility with Hastelloy X were conducted on graphite samples coated with molybdenum, niobium carbide, and zirconium carbide at 1750 deg F and 300 psi for 1000 and …
Date: December 30, 1960
Creator: Carpenter, R. & Del Grosso, A.
Partner: UNT Libraries Government Documents Department
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Process summary of Purex Plant operation, January 1961--December 1961

Description: This report describes Purex Plant operations at Hanford for January, 1961-- December, 1961. Solvent extraction and ion exchange processes and data are discussed.
Date: December 30, 1960
Creator: Geier, R. G. & Rathvon, H. C.
Partner: UNT Libraries Government Documents Department
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PT-IP-385-C, E-N reactivity matching measurement

Description: The projected E-N load at H Reactor will require a complete change in the type of charge placed in most flattened zone process tubes. Objective of this test is to determine the reactivity of the proposed E-N charge relative to the known natural uranium charge reactivity.
Date: December 30, 1960
Creator: Carter, R. D.
Partner: UNT Libraries Government Documents Department
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REACTOR FUEL WASTE DISPOSAL PROJECT-PERMEABILITY OF ROCK SALT AND CREEP OF UNDERGROUND SALT CAVITIES. Final Report

Description: A study was made of two problems of salt-cavity storage, namely, seepage of wastes out of formations and closure of cavities due to plastic flow of salt. The results indicate that both problems are negligible; bedded salt is more impermeable than dome salt. Kerosene was found to be nonreactive with dome salt whereas brine solutions showed some interaction. It is concluded that storage of radioactive wastes in salt cavities is feasible. (D.L.C.)
Date: December 30, 1960
Creator: Reynolds, T.D. & Gloyna, E.F.
Partner: UNT Libraries Government Documents Department
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KER-4 operating report test K-4-8, PT-IP-300-A

Description: Objective of the test was to determine and evaluate the behavior of 8 20-inch fuel elements during irradiation using the hot-headed end closures on the inner tube.
Date: December 29, 1960
Creator: Young, K. L.
Partner: UNT Libraries Government Documents Department
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Analysis of E-N loadings

Description: Three E-N loaded tubes were dissolved, sampled and analyzed, starting November 9, 1960. The results of these analyses and an explanation of the methods used are the subject of this report. Each tube loading received an identification code in each facility in which it was processed. All of these codes are listed for future reference. Each batch of slugs was dissolved in a preflushed dissolver. When complete solution was indicated by a leveling off of the specific gravity, two 1 ml samples were taken and analyzed for uranium, specific gravity, and excess nitric acid. The dissolver charge was digested an additional four hours. At the end of the digestion period, two 1 ml samples and one 20 ml pig sample were taken. The three samples were analyzed for U, SpG, and HNO{sub 3}. Agreement between these samples and the previous samples was taken as confirmation of complete dissolution and representative sampling. If agreement was not obtained, sampling was continued. After verification of the pig sample, six 1 ml aliquots were taken for analysis by the Analytical Control group. The remainder was aliquoted to provide material for mass analysis and for analysis by the Process Chemistry group.
Date: December 28, 1960
Creator: Zimmer, W. H.
Partner: UNT Libraries Government Documents Department
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Optimization Studies on Paste-Fueled Fast Reactors

Description: The reference design is an unmoderated, sodium-cooled reactor using a paste fuel of uranium monocarbide in sodium. The core is a cylinder 5 ft in diameter and 5 ft in height. An 18-in. thick breeding blanket surrounds the core, and an 18-in. thick graphite reflector surrounds the blanket. Various changes were made in the reference core to uncover any possible modifications for cost reductions and to evaluate the consequences of certain design modifications which might occur. Cases were studied for variations in: fuel volume fraction in the core from 0.2 to 0.6; fertile material volume fraction in the blanket from 0.2 to 0.6; blanket thickness 3 in. to 24 in.; fuel materials of UC, U metal, UC/ sub 2/, PuC-- UC, Pu-- U metal, and PuO/sub 2/-- UC/sub 2/; and liquid carrier in the paste of Na, Sn, or Pb. (auth)
Date: December 28, 1960
Creator: Zetterbaum, J. M. & Kerlin, T. W.
Partner: UNT Libraries Government Documents Department
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Aerodynamic Re-Entry Analysis. Task 2. Thermoelectric Generator Summary Report

Description: An analytical trajectory and aerothermodynamic analysis of a satellite containing a Task 2 thermoelectric generator was completed. A 300-statute mile circular polar orbit was used for this analysis and the launch was assumed to be from Vandenberg Air Force Base. Results of this study show that upon natural decay from a successful mission, the radio-cerium fuel will burn up in space at high altitude, thus only a very minor amount of radio cerium will be released to the stratosphere. A complete analyses of the fate of the radio-cerium fuel following various aborted launching attempts also was carried out. Charts summarizing the various assumed failures and locations of the fuel following failure are shown. A technical discussion of the methods used in performing the analysis is included in the report. (auth)
Date: December 27, 1960
Creator: Oehrli, R.
Partner: UNT Libraries Government Documents Department
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DISPERSION STRENGTHENING OF IRON-ALUMINUM BASE ALLOYS: A FEASIBILITY STUDY

Description: The feasibility of improving the mechanical properties at 1700 to 1800 deg F of oxidation-resistant Fe-Al-Cr alloys by means of a refractory dispersion was explored. A literature search was conducted, preliminary experimental determinations of properties of the alloy and its oxides were carried out, and certain mathematical relations between dispersion charaeteristics and metallurgical variables were derived. The results indicate that the alloys can be strengthened sufficiently by using a dispersion with an interparticle spacing of about 2 to 3 mu . High-temperature native oxides of the Fe-Al-Cr alloy consist largely of Al/sub 2/O/sub 3/ and in theory would serve as a aatisfactory second phase. (auth)
Date: December 27, 1960
Creator: King, B.
Partner: UNT Libraries Government Documents Department
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Final Report on the Pinot Experiment

Description: The Pinot Project was designed to provide some indication of the extent to which gases from a confined underground explosion in oil shale would migrate parallel to the bedding planes. At 0800 on Aug. 2, 1960, 946 lb of nitromethane was fired in shot hole No. 1. There was no visible damage to the mine adit or to any structure associated with cation of the extent to which gases from a confined underground explosion in oil shale would migrate parallel to the bedding planes. At 0800 on Aug. 2, 1960, 946 lb of nitromethane was fired in shot hole No. 1. There was no visible damage to the mine adit or to any stnucture associated with the workings. Gas samples collected from sampling holes near the shot hole were analyzed for Kr/sup 85/, which had been included with the nitromethane as a tracer. It appeared that the Kr/sup 85/ concentration in the samples out to 50 ft was more or less independent of space and time between +2 and +50 hr. Relativsly little Kr/sup 85/ was detected at 125 ft and none beyond. About (20 plus or minus 10)% of the Kr/sup 85/ escaped into ths adit. The results of the Pinot experiment cannot be extrapolated quantitatively to the case of a nuclear explosion in oil shale. Even if the structure at the Pinot site is typical of oil shale, the generation of a smaller quantity of noncondensible gases per unit energy in a nuclear explosion (as compared with a chemical explosion), the shonter time scale of the ensrgy release and the higher temperatares and pressures encountered will all have a definite influence on the effective containment distance. One can conclude, however, that, if the medium at the site of a potential nuclear experiment is similar to that at Pinot, …
Date: December 27, 1960
Creator: Adelman, F. L.; Bacigalupi, C. M. & Momyer, F. F.
Partner: UNT Libraries Government Documents Department
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Loading and operating conditions for NIN-1 and NIE-1 elements in the KER loops under PT-IP-377-A

Description: This document provides the loading and operating conditions for eight 16-inch or five 24-inch elements, either natural NIN-1 or .947% enriched NIE-1, in any of the four KER loops. The loadings are tabulated; operating conditions for either charge in KER 2, 3, 4, or 1 are given in figures.
Date: December 23, 1960
Creator: Kratzer, W. K.
Partner: UNT Libraries Government Documents Department
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Vapor Pressures of the Rare Earths

Description: Abstract: This report presents the vapor pressures versus temperature data graphically for the rare earth elements, yttrium and scandium.
Date: December 23, 1960
Creator: Beavis, L. C.
Partner: UNT Libraries Government Documents Department
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A CORROSION STUDY OF WELDED STAINLESS STEEL FUEL ELEMENTS

Description: Fuel element corrosion studies designed to and in selecting and evaluating SM-2 fuel element welding techniques are discussed. Tests on type 347 ss plate type fuel elements welded by the selected tungsten inert gas technique showed good corrosion integrity of specimens under a variety of conditions including a 500-hr test under simulated SM-2 conditions of flow and coolant chemistry. (auth)
Date: December 22, 1960
Creator: Bergen, C. R.
Partner: UNT Libraries Government Documents Department
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Molten-Salt Reactor Program Quarterly Progress Report: July 1960

Description: Report containing ongoing projects and experiments undertaken by the Oak Ridge National Laboratory's Molten-Salt Reactor Program.
Date: December 22, 1960
Creator: Oak Ridge National Laboratory
Partner: UNT Libraries Government Documents Department
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Semi-final report (report No. 3) E-N load conversion ratios

Description: Experimental data on plutonium yield and U{sup 235} burnout are now available on the E metal portion of three central zone striped E-N columns and one fringe blanket E column. These data and an overall E-N load conversion ratio based on experimental data are now reported.
Date: December 22, 1960
Creator: Nechodom, W. S.
Partner: UNT Libraries Government Documents Department
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Chemical Processing Department Monthly Report: November 1960

Description: This report, from the Chemical Processing Department at HAPO for November 1960, discusses the following: Production operation; Purex and Redox operation; Finished products operation; maintenance; Financial operations, facilities engineering; research; employee relations; and special separation processing and auxiliaries operation.
Date: December 21, 1960
Creator: Hanford Atomic Products Operation. Chemical Processing Department.
Partner: UNT Libraries Government Documents Department
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In-Pile Corrosion Test Loops for Aqueous Homogeneous Reactor Solutions

Description: An in-pile corrosion test loop is described which is used to study the effect of reactor radiation on the corrosion of materials of construction and the chemical stability of fuel solutions of interest to the Aqueous Homogeneous Reactor Program at ORNL. Aqueous solutions of uranyl sulfate are circulated in the loop by means of a 5-gpm canned-rotor pump, and the pump loop is designed for operation at temperatures to 300 ts C and pressures to 2000 psia while exposed to reactor radiation in beam-hole facilities of the LITR and ORR. Operation of the first loop in-pile was begun in October 1954, and since that time 17 other in-pile loop experiments were completed. Design criteria of the pump loop and its associated auxiliary equipment and instrumentation are described. In-pile operating procedures, safety features, and operating experience are presented. A cost summary of the design, fabrication, and installation of the loop and experimental facillties is also included. (auth)
Date: December 21, 1960
Creator: Savage, H.C.; Jenks, G.H. & Bohlmann, E.G.
Partner: UNT Libraries Government Documents Department
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