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The Identification and Determination of Trace Amounts of Rare Earth Elements in Graphite by Neutron Activation

Description: Abstract: "A method is described for the identification and quantitative determination of trace amounts of rare earths in graphite by measurement of the energies and decays of the activities induced by neutron irradiation. The specific rare earth elements identified are europium and samarium. During the development of this method, the half-lives of Eu-152 and Sm-153 were determined. These are reported as 9.32 +/- 0.04 hours and 46.34 +/- 0.23 respectively."
Date: September 1, 1949
Creator: Ross, A. M.
Item Type: Refine your search to only Report
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Exploratory Scavenging Studies for the Decontamination of Redox Solutions

Description: From introduction: "This report is concerned with exploratory experiments designed to studies the efficiency of a number of scavengers for zirconium and niobium adsorption and to provide preliminary information on the best conditions to employ on the most satisfactory of those scavengers studied, namely Super Filtrol FO. The data in this report include data obtained through October, 1949, and are by no means considered to be final. The investigation is currently being actively continued."
Date: May 1, 1950
Creator: Roake, W. E. & Lowe, C. S.
Item Type: Refine your search to only Report
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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
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The Development of Plutonium Electrodeposition Methods : Interim Report

Description: From introduction: "The following report presents a body of information obtained in the Health Instrument Development Laboratory from September, 1948, to the present, and is intended to be a preliminary review of [the study of electrodeposition of plutonium]. Many improvements in technique and methods and investigations along lines not explored are suggested by the present work. These will be undertaken as time permits, and reported at a later time."
Date: March 1, 1950
Creator: Schwendiman, L. C.
Item Type: Refine your search to only Report
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The Determination of U²³⁷ and Fission-Product Contamination in Uranium Recovered by the Redox Process

Description: Introduction: "When uranium slugs are irradiated in the Hanford piles, one of the many substances formed is U-237. It arises primarily from the reaction: U-238 (n,2n) U-237. This uranium isotope is a beta and gamma emitter with a half-life of 6.7 days. Because it is isotopic with U-238, it accompanies the uranium recovered by the Redox Process, and its concentration is, of course, not diminished by the fission-product decontamination cycles. As a consequence, the maximum total decontamination … more
Date: October 1, 1952
Creator: Leboeuf, M. B.
Item Type: Refine your search to only Report
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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
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Accumulation of Radioactivity in Columbia River Fish in the Vicinity of the Hanford Works

Description: Abstract: The data obtained from the radioassay of fish collected in vicinity of the Hanford Works between April, 1948 and June, 1950 are presented. Most of the radioactivity in the fish resulted from the concentration of p32 in the scales, bone, and certain visceral organs. The level of activity density in the fish was influenced by size, feeding habits and metabolic rate in addition to the activity density of the water. Changes in operation of nuclear reactors have resulted in progressive inc… more
Date: July 1, 1952
Creator: Olson, P. A., Jr. & Foster, Richard F.
Item Type: Refine your search to only Report
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Corrosion of Construction Materials in TBP (HW-3 Flowsheet) Process Streams

Description: Introduction:"A corrosion test program to determine the effect TBP process streams, which contain chlorides, have upon the corrosion resistance of several construction materials, was completed. Data are presented on the performance of Carpenter 20, T-309SCb, T-347. T-316 and tantalum in the RAF and RAW process streams and on the performance of titanium and zirconium in the RAW stream."
Date: November 1, 1950
Creator: Koenig, W. W. & Sanborn, K. L.
Item Type: Refine your search to only Report
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Final Report : Production Test 105-329-F, Filled Block Graphite Sample Report

Description: This report provides data on production test 105-329-P and solid graphite samples used to analyze damage obtained from controlled natural erosion tests. The data provided will help establish current ideas on the status of filler block graphite and interpretation of the data will assist in establishing pile operating temperature limits based on stored energy.
Date: November 1, 1950
Creator: Johnson, P. A.
Item Type: Refine your search to only Report
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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
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Welding Characteristics of Zircaloy Jacketed Fuel Elements

Description: Contemplated higher tube power for future reactor operation will probably require a fuel element jacketing material more corrosion resistant than presently available aluminum alloys. Zirconium and its alloys are generally regarded as the most promising jacketing candidates for high temperature operation, particularly for exposures of long duration. In order to obtain assembly, welding, and corrosion data, twenty Al-Si bonded and twenty unbonded Zircaloy fuel elements were prepared for KER loop … more
Date: July 1, 1956
Creator: Lingafelter, J. W.
Item Type: Refine your search to only Report
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Nuclear Safety of Right Elliptic and Right Annular Cylinders

Description: Past experience has shown that the demand for increase separations plant capacity comes up very regularly. One of the variables which greatly affects plant capacity is cross-sectional area of the individual vessels. Larger areas permit greater flow rates as well as more space for the installation of heat transfer piping (shell and tube concentrators). Design considerations of the separations plants vessels have been based on both circular cylinder and slab geometries. A study has been made to d… more
Date: June 1, 1956
Creator: Ketzlach, Norman
Item Type: Refine your search to only Report
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Irradiation of U-Mg Matrix Fuel Materials to High Exposures

Description: An experiment designed to evaluate the in-pile performance of the U-Mg fuel material when irradiated to high burnups has been completed. Twelve specimens of the fuel material which contained uranium particles that packed 50 volume per cent, (91.5 weight per cent), uranium in a magnesium matrix were canned in Zircaloy cans and irradiated in the Materials Testing Reactor to 0.1 (1000 MWD/T), 0.3 (5000 MWD/T), 1.0 (10000 MWD/T) and 2.0 20000 MWD/T) per cent burnup of the total uranium atoms; more … more
Date: August 1, 1956
Creator: Freshley, M. D. & Last, G. A.
Item Type: Refine your search to only Report
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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
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An Evaluation of Buried Waste Line Design Practice Interim Report No. 2: Underground Pipeline and Structure Corrosion Study Program

Description: This report has been prepared to review the status of design for buried waste line and presents the major factors involved in support of the conclusions. This report is the second in a series reporting on the general subject of underground corrosion. The first on cathodic protection of waste lines noted the technology of stainless steel and its effect on existing waste line and recommended continued use of the cathodic protection. Experience with buried stainless pipe had shown that, unless pro… more
Date: April 1, 1955
Creator: Jaske, R. T.
Item Type: Refine your search to only Report
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Proposed Revision in Computations of MPC's for Long-Lived Radioisotopes

Description: Equations are developed for the computation of MPC's for radioisotopes assuming the excretion or retention to follow a power law rather than an exponential law. Computations are made for four isotopes on which some human data are available. Uncertainties in the initial data due to the use of intravenous injection to obtain the primary data, the definition of retention and the effects of age and diet are discussed.
Date: March 1, 1955
Creator: Healy, J. W.
Item Type: Refine your search to only Report
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