58 Matching Results

Search Results

Results: 1 - 24 next
open access

Comments on Equipment for a PRTR Water Quality Control Laboratory

Description: This document describes required laboratory space and lists major equipment items necessary for a routine water quality laboratory in the P. R. T. R. Building. During discussions with R. D. Widrig and V. L. Rooney about the analytical sample program for the Plutonium Recycle Test Reactor, the author was asked to summarize equipment and space needs for a water control laboratory to provide routine analytical coverage on some of the water systems. Based upon 1706-KE-KER experience, some operating… more
Date: December 1, 1959
Creator: Anderson, H. J. & Peray, R. E.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Halogen Collector Test Program

Description: Report documenting the Halogen Collector Test program, which was undertaken to provide "methods of removing trace quantities of radioactive iodine from an air stream" (p. 1). The report includes designs of the program and the test facility, test results, analysis of these results, and encountered problems. Appendices begin on page 38.
Date: March 1, 1960
Creator: Arthur D. Little, Inc.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Crack Propagation Tests ofZincaloy-2 Reactor Pressure Tubing in Both the Normal and Hydrided Conditions

Description: The purpose of this document is to discuss the problems of crack propagation, and catastrophic brittle fracture and to discuss tests that are designed to predict the ability of the material to resist brittle fracture.
Date: June 1, 1954
Creator: Aungst, R. C. & Defferding, Leo J.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Experimental Program for the PRTR Gas Loop

Description: Early in the U.S. gas-cooled reactor program, it was recognized that a considerable research and development effort would be needed to utilize the full potential of gas cooling. Hanford Laboratories contribution to this program began in August, 1958 when a graphite studies program was initiated. The primary objectives of the Hanford program are: (1) to secure improved knowledge of the reaction of gas coolants with protected and unprotected graphites over a range of conditions of practical inter… more
Date: September 1, 1959
Creator: Baker, D. E.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Thermal Hydraulic Bases for Selected PRTR Process Specifications

Description: This document presents the bases for those PRTR Process Specifications involving considerations of heat transfer and fluid flow. It will be noted that some of the bases incorporate information gained from laboratory experiments with electrically heated test sections simulating PRTR fuel elements. These experiments are described in some detail elsewhere.
Date: April 1, 1960
Creator: Batch, J. M. & Ambrose, T. W.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Effects of Reactor Environment on Candidate PRTR Gas Loop Materials.

Description: The purpose of this program is to determine the effects of neutron radiation and reactor gaseous atmospheres on the structural integrity of candidate materials for the PRTR gas-cooled loop. An exploratory investigation is being conducted to select a high temperature resistant alloy for the fabrication of tubes and supporting appliances for the PRTR gas-cooled loop. In addition to a low neutron cross section, the material must be able to withstand the operating conditions outlined in Table 1.
Date: September 1, 1959
Creator: Bement, A. L.; Wheeler, K. R. & Pessl, M. J.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

The Use and Calibration of Scintillation Counter--Model Y

Description: Several improvements have been made in the gamma scintillation counter (GSC). The Model V gamma scintillation counter uses a canned thallium activated sodium iodide crystal as a detector. Although the electronic components remain unchanged, a modification of the sample support has been made to improve reproducibility of geometry. To assure comparable results between various counters, they must be operated at the same energy threshold and counting yield. Methods have been developed to assure… more
Date: August 1, 1953
Creator: Brauer, F. P. & Leboeuf, M. B.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Subsurface Geology of the Hanford Separation Areas

Description: The region in which Hanford's chemical processing plant areas (separation areas) are located in the central portion of the Hanford Works area on a plateau, shaped like a giant bar, of glaciofluviatile materials. The general locations of these areas is shown in Figure 1. The region studied rises from 200 to 300 feet above the surrounding area and encompasses approximately 40 square miles or somewhat less than 8% of the Hanford reservation (Figure 2). Within the region are located the chemical se… more
Date: October 1, 1959
Creator: Brown, D. J.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

The Use of Tetravalent Uranium and Hydrazine as Partitioning Agents in Solvent Extraction Process for Plutonium and Uranium

Description: In solvent extraction purification processes such as are used at Hanford, the fuel elements or "slugs" from the reactor containing uranium, plutonium, and fission products are dissolved in nitric acid, adjusted to the required feed composition, and pumped to the solvent extraction columns. Figure 1 in a schematic diagram of such a solvent extraction process. In the A column, the uranium and the plutonium are extracted into an organic phase while the bulk of the fission products remain in the aq… more
Date: February 1, 1959
Creator: Buckingham, J.S.; Colvin, C.A. & Goodall, C.A.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Nitrous Acid Behavior in Purex Systems

Description: In HAPO solvent extraction processes there are two independent aspects of nitrous acid chemistry. One concern the decomposition of the solvent through nitration reactions and the attendant problems. These reactions are autocatalytic in the presence of nitric acid and have threshold values for both temperature and nitric acid concentration for a given solvent below which nitrous acid disappears and above which it is generated with continuous destruction of the solvent. These reactions are ident… more
Date: May 1, 1959
Creator: Burger, L. L. & Money, M. D.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Properties of the System - Uranyl Nitrate - Aluminum Nitrate - Nitric Acid - Water - Hexone. Part VII. Distribution of Uranyl Nitrate, Nitric Acid, Plutonium (IV) and Plutonium (VI) from 0 to 60°C.

Description: This report discusses studies regarding the distribution and other properties of uranyl nitrate, nitric acid, plutonium (IV) and plutonium (VI) as part of the Redox Process that separates plutonium, uranium, and fission products.
Date: February 1, 1952
Creator: Burger, L. L.; Rehn, I. M. & Slansky, C. M.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

The Coulometric Determination of Acid

Description: Introduction: "The need for a method of acid determination which could be used for small samples and easily adapted to remote control led to the investigation of the use of electrolytically generated base for the titration of acid in certain solutions. The use of electrolytically generated base for the titration of acetic acid in the presence of nitric acid has been reported (1)."
Date: March 1, 1950
Creator: Carson, W. N. & Ko, Roy
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Microtitration of Free Acid in Uranyl Nitrate Solutions

Description: The approaches to the solution of the problem of removing or nullifying the effect of the hydrolysis of uranyl ion on acid titrations were: 1) use of a complexing agent and titration technique suitable for micro samples; 2) addition of a reagent that reacts with uranium to release 1 or 2 equivalents of acid per mole of uranium present (this permits correcting the titration value for the acid contributed by the uranium, or conversely permits an alkimetric titration of uranium); 3) separation of… more
Date: October 1, 1953
Creator: Carson, W. N., Jr.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Report on HAPO Unitized Microfilm Drawing System

Description: This report is being submitted to provide information and data on the planning and installation of a new mechanized drawing system which utilizes a new drawing index system and a 35mm microfilm image in a standard IBM card. The communication of engineering information to date has been primarily the full size contact print produced by exposing and developing light sensitive material. This method produces legible copies; but, it has the following disadvantages : (a) the original drawings are frag… more
Date: October 1, 1959
Creator: Durbin, J.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Manual of Radiation Protection Standards

Description: "The following is an alphabetical listing of terms and units in common usage at Hanford Atomic Products Operation. Other terms and definitions may be added as the need becomes apparent or as revisions or additional terms are issued by the NCRP and ICRP."
Date: March 1, 1960
Creator: General Electric Company
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Autoclave Corrosion Behavior of U-Low Carbon and U-Low Zirconium Alloy Fuels

Description: A preliminary evaluation of the autoclave corrosion behavior of a series of U-low C alloys and a series of U-low Zr alloys prepared by Fuels Fabrication Development Operation has been made. The corrosion testing was conducted by Coatings and Corrosion Operation by the experimental methods and procedure outlined in HW-61378.
Date: December 1, 1959
Creator: Goffard, J. W.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Physical Properties of the System Uranyl Nitrate - Aluminum Nitrate - Nitric Acid - Water - Hexone: Part 6. Distribution Coefficients of Plutonium(IV) Nitrate

Description: Report discussing the properties of plutonium and plutonium's distribution between hexone and aqueous phases, which relates to the function of Redox plants
Date: December 1, 1950
Creator: Groot, C.; Rehn, I. M. & Slansky, C. M.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Specifications for Vibrationally Compacted, Mixed Oxide (UO2-PuO2), Fuel Elements for the Plutonium Recycle Test Reactor (MARK I-L)

Description: Report describing the dimensions, materials, and fabrication of vibrationally compacted, mixed oxide (UO2-PuO2) fuel elements for the Plutonium Recycle Test Reactor (MARK I-L). Appendix begins on page 38.
Date: October 1, 1963
Creator: Hanford Atomic Products Operation
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Final Report A CG-791 Containment Test

Description: This report describes and evaluates the Hanford 105 reactor building structures' ability to withstand an internal pressure increase. The means by which their roof and wall surface would contain a pressure buildup 0.3 psi, and prevent contaminant release which might accompany a nuclear incident are discussed. Prototypes of the B, D, DR, F, and H reactor block wall configuration, the corrugated transite roof of the K reactors, and the corrugated transite walls of the K and C reactors are evaluate… more
Date: January 1, 1960
Creator: Jensen, H. F.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
Back to Top of Screen