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Hanford Works Analytical Manual for Reactor Process Water

Description: Purpose: "The Hanford Works Analytical Manual for Process Water is designed to specify the analytical methods to be applied for control purposes in the Reactor Section, Process Sub-Section laboratories. The procedures are in general form and serve as references rather than outlined laboratory instructions. The manual us designed to replace the "Hanford Works Manual," HW-12862."
Date: February 13, 1953
Creator: Hanford Works
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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DC Bridge NPR Horizontal Rod Counting

Description: This report is a summary of work done for system development on the NPR ball safety backup for the horizontal rods. This phase of the system development is limited to discussion of the horizontal rod counting circuitry utilizing a direct current bridge network.
Date: July 24, 1959
Creator: {{{name}}}
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Ferrous Sulfamate Stability in the RA System

Description: Objective: "The observations summarized in the present report were made to determine the stability of ferrous and sulfamate ions and sulfamic acid in RA Column scrub solution (RAS) and in aqueous solution comparable to the RA Column feed tee composition (RAFS). Knowledge of the stability of the reducing agent (ferrous iron) is necessary to properly plan the method of preparation and introduction of this component into the RA system and to assure dependable and reproducible performance."
Date: April 20, 1950
Creator: Clagett, Fred
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Corrosion Tests : SAE 1010 Mild Steel in Synthetic Neutralized Redox Waste Solution

Description: From introduction: "This report gives the results of a 1000-hour corrosion test of SAE 1010, low carbon steel, in synthetic Redox waste solutions...The present test was designed to obtain corrosion rates for waste solution temperatures of 180 F, 200 F, and 220 F in solutions neutralized to pH values of 11, 12, and 13.
Date: November 13, 1952
Creator: Endow, Noborn
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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A Two-Group Calculation of the Transients in an Externally Driven Reactor with Reflector

Description: Summary: "Expressions for the fast and thermal flux in the core of an externally driven, symmetrical infinite slab reactor with a reflector are derived as a function of the reflector thickness. The driver is represented by an inward current of fast neutrons through the outer boundary of the reflector. The flux distribution curve is plotted for several values of reflector thickness. The object is to determine the effect of changing reflector thickness on the flattening of the flux inside of the … more
Date: 1960
Creator: Norbeck, Edwin
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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The Engineering Properties of Iron-Limonite Concrete for Construction of Biological Shields

Description: Introduction: "This letter is intended to provide a brief summary of the information presently available on the engineering properties of iron-linonite concrete with the view of adapting such concrete with the view of adapting such concrete for use as biological shielding material in a Hanford pile. By reducing materials and fabrication costs, such a adaptation might effect a savings of at least two million dollars per pile over the present iron-masonite laminated shield structure."
Date: January 30, 1952
Creator: Warren, Curtis
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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PRTR Fuel Element Nuclear Safety

Description: A study of the nuclear safety in the storage and transportation of PRTR fuel elements has been made. This study was based on 7-rod clusters of plutonium-aluminum allow fuel elements containing 1.8 per cent Pu by weight. Each cluster is 7 feet 4 inches in length and contains 270 grams plutonium. Drawings of the "New Fuel Storage Pit" (H-3-11030) have been reviewed for nuclear safety. Nuclear safety criteria for the design of a lead shielded fuel transfer cask as well as criteria for the storage … more
Date: March 30, 1959
Creator: Ketzlach, N.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Division of Reactor Development Programs Monthly Report- May 19599

Description: Plutonium Fuels Development Basic studies. Experiments to determine the effect of plutonium dioxide additions on the sinterability of UO2 have continued. PuO2 has been added to ball milled PWR grade UO2 as a physical mixture, and in the form of the mixed crystal oxide.
Date: June 15, 1959
Creator: Lewis, M.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Design and Evaluation of HAPO Canned Motor

Description: The transfer or circulation of raw dissolver solutions containing gross particulate matter presents many problems not easily overcome by standard pumping equipment. In April of 1956 the HAPO concept of a modified Archimedes screw pump was developed. Two basic models, externally powered and driven through extended shafts, were constructed and tested. Operation of these preliminary models was so satisfactory that a third unit, integrally formed into drive motor, was built and placed in extended … more
Date: June 19, 1959
Creator: Dunn, J.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Development and Preliminary Testing of Powder-Lock Feeder

Description: At the request of 234-5 Development, studies of a system for controlling plutonium powder transfer were undertaken by Process Equipment Development. This report presents details of equipment designed to fulfill requirements and proposes equipment for installation on additional Hot Button Line prototypes.
Date: April 3, 1959
Creator: Dunn, J.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Plutonium Recovery from Contaminated Materials Project CGC-813-Scope Revision No. 2

Description: An inventory of the contaminated materials accumulated since the initiation of this project in June 1958, revealed a larger variety and quantity of materials that could be burned, than was specified for the initial scope. Therefore, it is desirable to revise the scope to permit handling the majority of these materials with the initially installed equipment.
Date: January 23, 1959
Creator: Doud, E.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Flow Decay After an Electrical Power Outage in the PRTR

Description: Previously, W. S. Figg and T. W. Ambrose (HW-51767 Rev) have investigated the problem of flow decay following electrical power loss to the PRTR primary coolant pumps. However, since the time of their study many reactor piping changes have been made in the design; therefore, it has become advisable to re-examine the problem incorporating these changes.
Date: February 6, 1959
Creator: Muraoka, J.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Random Loading of E-Metal Dissolver

Description: Nuclear safety in the dissolution of irradiated 0.95 U235 enriched fuel has been investigated. In particular, critical conditions of fuel of this enrichment in a 52-inch diameter dissolver crib were studied. Since a crib this size is not safe by geometry, dissolution procedures as well as maximum safe batch sizes were analyzed. Uranium-water lattices are normally studied in systems in which rods are uniformly dispersed in the moderator. The results of such a study for 1.34-inch diameter solid … more
Date: February 25, 1959
Creator: Ketzlach, M.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Neutron Age Calculations. (Homogeneous Systems)

Description: In an earlier study on criticality conditions for homogenous mixtures, 2/cm^2 was used as the neutron age for all mixtures of water and uranium. At the higher H/U ratios (low uranium concentration), the calculated critical parameters were in good agreement were in good agreement with experimental data. At the low H/U ratios (high uranium concentrations) the calculated critical parameters were smaller than the experimental ones (more conservative from a nuclear safety point view). These results … more
Date: July 10, 1959
Creator: Ketzlach, N.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Division of Reactor Development Programs Monthly Reports-June 1959

Description: Basic Studies. Sinterability experiments in the system UO2-PuO2 have continued, and data are available at one hour hold times across the UO2-PuO2 composition limits. Sintered densities appear to be markedly dependent on pressed densities with densification occurring very rapidly at higher pressing pressures. The following table illustrates the effect of one hour at temperature on final density for pure plutonium dioxide pressed to both 40 and 60 percent of theoretical density.
Date: July 15, 1959
Creator: Lewis, M.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Urine Analysis for Tritium Oxide

Description: This report analyzes a procedure based on the production of acetylene from the active water, with subsequent measurement of the ionization caused by the tritium beta particle. This eliminates the troublesome absorption on the chamber walls when hydrogen is used, and provides a rapid method for the preparation of the urine samples.
Date: July 27, 1949
Creator: Healy, J. W.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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