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K Reactor moderator distortion study

Description: Irradiation-induced moderator distortion has plagued the Hanford reactors from their earliest days until the present. The first-manifestation of graphite distortion was in the form of expansion of the B, D and F stacks. It was found that expansion was very temperature-dependent and could be reversed by raising the graphite operating temperature. The DR, H, C and K Reactors were designed with provisions to minimize, or accommodate expansion. It was not until after the K Reactors had been designe… more
Date: June 22, 1964
Creator: Alexander, W.K. & Russell, A.
Partner: UNT Libraries Government Documents Department
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Density and Hydrogen Content of Uranium Oxide Cakes and Slurries

Description: The work described was undertaken to provide data for nuclear safety studies concerning NPF reprocessing equipment. The original objective was to determine the uranium density and water (hydrogen) content of UO2-H2O mixtures ranging from compact centrifuge cakes to dilute slurries. The scope was later expanded to include mixtures of UO2 with hydrocarbon oil and mixtures of UO3-H2O.
Date: March 22, 1960
Creator: Amos, L. C.
Partner: UNT Libraries Government Documents Department
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Production test-080 - physics tests at D reactor deactivation interim report - experimental data

Description: Production Test-080 authorized the conduct of certain physics tests during the deactivation of D Reactor. The primary objective of the test was to measure certain physics parameters which could be used to check current computational models. In this report are presented a brief chronology of the tests and a tabulation of the experimental data. In general, data processing has not progressed beyond simple reduction of the raw experimental data to a form more easily used in future analytical compar… more
Date: September 22, 1967
Creator: Bailey, G. F.
Partner: UNT Libraries Government Documents Department
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Apparatus for the Study of Fission-Gas Release From Fuels During Postirradiation Heating at Temperatures Up to 1600 C

Description: An apparatus to study rare-gas fission-product release from nuclear fuel materials during postirradiation heating was developed. Xenon and krypton fission gases escaping from a small specimen during heating at constant temperature are measured using a continuous radioactivity monitor and charcoal adsorption traps. The rhodium-wound furnace is capable of operation at 1600 deg C. Helium carrier gas is purified by activated alumina, copper, and zirconium traps, and the oxygen and moisture contents… more
Date: July 22, 1960
Creator: Barnes, R. H. & Sunderman, D. N.
Partner: UNT Libraries Government Documents Department
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Piping changes for increased production at B, D, DR, F, C, and H reactors

Description: This study proposes improvements in the process water piping adjacent to the front and rear faces of these reactors. This report covers the external piping of the reactors from the incoming valve pit to the inlets of the outgoing retention basins.
Date: January 22, 1960
Creator: Bauer, G. H.; Harrison, C. W.; Hill, V. R.; McLenegan, D. W. & Mondt, J. F.
Partner: UNT Libraries Government Documents Department
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Observations on the Response of Two P-NJunction Diodes to Protons

Description: The response of a two silicon p-n junction diodes has been measured for protons up to 13.3 Mev. In one case the dependence of depletion layer thickness with bias voltage was found to be T or V(0.46). The observed resolution, made up of contributions from crystal noise, beam width, and scatterer thickness, was about 1% for 9-Mev protons.
Date: November 22, 1960
Creator: Benveniste, J.; Booth, R. & Mitchell, A. 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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Aerospace Nuclear Safety

Description: This report talks about the Aerospace Nuclear Safety
Date: September 22, 1965
Creator: Blake, V. E., Jr.
Partner: UNT Libraries Government Documents Department
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Proposed irradiation of substandard fuel elements. Phase 2

Description: The reference letter outlined an initial proposal for irradiating limited categories of substandard fuel elements in the upstream positions of the reactor process tubes. As Phase 2 of this program, a comprehensive study has been made of all current fuel reject categories with respect to use in the upstream low rupture potential positions. This report describes additional ``reject`` fuel categories, the estimated cost savings, rupture potential, and procedures for identifying and handling pieces… more
Date: April 22, 1963
Creator: Blanton, W. A. & Weakley, E. A.
Partner: UNT Libraries Government Documents Department
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Beam Separators for Bev Particles

Description: The problem of separation of beams of particles of different masses but of the same momentum at Bev energies is the subject of a great deal of study at several high energy laboratories. In this note we shall describe the problem and tabulate a few of the cogent parameters. Frequently the student of high energy interactions is faced with a beam of miscellaneous particles coming from an accelerator. By standard techniques this beam can be rendered approximately parallel and an inch or so in diame… more
Date: January 22, 1963
Creator: Blewett, J. P.
Partner: UNT Libraries Government Documents Department
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The plutonium nitride problem

Description: The WPE progress report for September, 1962 documents reasons for suspecting nitrogen as a possible cause of weapons fabrication difficulties and loss of production caused by radio-graphic rejects. This is a summary and documentation of the ``Nitride Problem`` and related subjects concerning fabrication metal. It contains the background information leading to details published in the Weapons Process Engineering Progress Reports. This summary may provide a better understanding of the problem, si… more
Date: March 22, 1963
Creator: Bond, R. H.
Partner: UNT Libraries Government Documents Department
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EVALUATION OF ULTIMATE DISPOSAL METHOD FOR LIQUID AND SOLID RADIOACTIVE WASTES. PART I. INTERIM LIQUID STORAGE

Description: As the first part of a study to evaluate the economics of the various steps leading to and including the permanent disposal of high-activity liquid and solid radioactive waste, costs of interim liquid storage of acid and alkaline Purex and Thorex wastes were estimated for storage times of 0.5 to 30 years. A 6- ton/day plant was assumed, processing 1500 tons/year of uranium converter fuel at a burnup of 10,000 Mwd/ton and 270 tons/year of thorium converter fuel at a burnup of 20,000 Mwd/ton. Tan… more
Date: August 22, 1961
Creator: Bradshaw, R.L.; Perona, J.J.; Roberts, J.T. & Blomeke, J.O.
Partner: UNT Libraries Government Documents Department
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Acceptance test specifications for accelerometers

Description: This document outlines the Westinghouse Astronuclear Laboratory (WANL) specification and procedures for acceptance testing of accelerometers. All accelerometers that are to be used for reactor instrumentation shall meet the requirements of this specifications before being accepted.
Date: September 22, 1964
Creator: Burlas, T. C. & Karako, E. F.
Partner: UNT Libraries Government Documents Department
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Radial Temperature Profile of Sodium Pool Boiling Heater Assembly

Description: The radial temperature around a sodium reactor heater assembly submerged in water is calculated using a model of the heater cross section found by conformal mapping. Thermocouple readings were also analyzed. When the heat flux is 5 x 10/sup 5/ Btu/hr-ft/sup 2/, a radial temperature drop of about 680 deg C across the center of the thermocouple well is calculated and found to be within 6% of the experimental value. Since most of this drop is across the 0.001-in. helium gap between the heater and … more
Date: February 22, 1960
Creator: Cappel, H. H.
Partner: UNT Libraries Government Documents Department
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Potential for process tube burnout during transient conditions

Description: This report is an interpretation of data (flow, pressure, temperatures within a process tube during events affecting single tubes) as applied to the most severe (rapid) K-reactor transients which are credible. Analyses indicate that no fuel channel burnout will result from a BPA power loss to the process pumps.
Date: April 22, 1960
Creator: Carlson, P. A. & Jones, S. S.
Partner: UNT Libraries Government Documents Department
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