This system will be undergoing maintenance May 21st between 9:00AM and 12:00AM CDT.

Search Results

Advanced search parameters have been applied.
open access

AN INFORMATION STORAGE AND RETRIEVAL SYSTEM FOR IRRADIATION EFFECTS IN METALS

Description: An information storage and retrieval system (PIC) was developed, utilizing the IBM 7090 computer, for handling data pertaining to the effects of neutron irradiation on metals. The input includes a reference identification, an appropriate abstract or extract summarizing the article, code identification parameters analogous to those used by the ASM-SLA Literature Classification System, and special codes identifying relevant irradiation and testing parameters. The output contains the same data plu… more
Date: August 15, 1963
Creator: Bush, S. H.
Partner: UNT Libraries Government Documents Department
open access

Long-term neutron activation products of nickel-58

Description: Certain advantages, such as higher strength at elevated temperature, have led to the use of alloys containing large percentages of nickel as a replacement for aluminum components. One example is the Inconel sheathing of control rods for the Hanford reactors. Since some of these components may remain in a reactor several years prior to removal, the neutron-activation products resulting from multiple chain reactions may become important in determining the radiation exposure levels at discharge. T… more
Date: December 11, 1963
Creator: Morgan, W. C.
Partner: UNT Libraries Government Documents Department
open access

Production reactor process tube film composition and radionuclide inventory studies. Status report

Description: The discharge of radioactivity from Hanford production reactors to the Columbia River has been studied for a number of years. The primary purposes of these studied have been to learn of the factors influencing production reactor effluent radioactivity concentrations and to develop methods for lowering the discharge concentrations of these radionuclides. In 1962 the Coolant Systems Development Operation (CSDO) began work on this program to determine the in-reactor film compositions and the inven… more
Date: February 12, 1963
Creator: Perrigo, L. D.
Partner: UNT Libraries Government Documents Department
open access

Radioactive contamination in liquid wastes discharged to ground at separations facilities through June 1956

Description: This document summarizes the amounts of radioactive contamination discharged to the ground from separation facilities through June 1956. Detailed data for individual disposal sites is presented on a month to month basis for the period July 1955 through June 1956. The major disposal sites in separation facilities, total volume of waste discharged at each location, and the gross amounts of plutonium and fission products discharged to the ground since startup are listed. This same data are present… more
Date: August 13, 1956
Creator: Heid, K. R.
Partner: UNT Libraries Government Documents Department
open access

Items for over-all Redox contamination improvement

Description: In view of contamination difficulties within the Redox operation, number of items are being considered to improve this situation. It is the objective of this document to list and describe seven times which it is felt would contribute most toward improvement. It is also an objective to present for RDS-D-12 Group consideration the recommendations of representatives from Manufacturing, Technical, and Design in these matters with the expectation that a project proposal written in general terms for … more
Date: January 13, 1955
Creator: Rohrmann, C. A.; Wilson, B. D. & Merrill, E. T.
Partner: UNT Libraries Government Documents Department
open access

Nuclear metallurgy lectures. Chapter 9, Fabrication and heat treatment of uranium

Description: This chapter presents the highlights of the fabrication and heat treatment of uranium with emphasis on HAPO type core material. For pile use three properties of uranium are of prime interest; grain size, type and degree of preferred orientation, and the mechanical properties.
Date: May 12, 1955
Creator: Riches, J. W.
Partner: UNT Libraries Government Documents Department
open access

The sequential separation and determination of arsenic-76 and phosphorous-32 in reactor effluent water

Description: A procedure is described for the sequential separation and determination of Arsenic-76 and Phosphorous-32 in reactor effluent water. The analysis can be performed in less than one hour and the arsenic fraction is scanned immediately after separation on a multi-channel gamma spectrometer. The discrete gamma energy of .56 MEV for Arsenic-76 makes further purification unnecessary. The organic phase containing the Phosphorous-32 is dry mounted on a one-inch stainless steel dish for beta counting.
Date: June 12, 1962
Creator: Johnson, W. C. Jr.
Partner: UNT Libraries Government Documents Department
open access

Irradiation Processing Department monthly report, July 1962

Description: This document details activities of the Irradiation Processing Department during the month of July, 1962. A general summary is included at the start of the report, after which the report is divided into the following sections: Research and Engineering Operations; Production and Reactor Operations; Facilities Engineering Operation; and NPR Project.
Date: August 13, 1962
Partner: UNT Libraries Government Documents Department
open access

Redox contamination: Terminal status report

Description: The Redox ruthenium contamination problem has two distinct phases; the environs contamination as a result of stack emissions, and the in-canyon contamination which controls time and cost factors for plant maintenance. On stack emissions, the probability of serious environs contamination exists so long as the batch-type, permanganate headend ruthenium volatilization process is used. Knowledge of the characteristics of volatilized ruthenium is not adequate today to give complete assurance that th… more
Date: July 13, 1954
Creator: Anderson, C. R.
Partner: UNT Libraries Government Documents Department
open access

The less familiar elements in the Atomic Energy program

Description: Many factors are responsible for the rapid growth of analytical chemistry during the past ten to fifteen years (This report was written in 1953). One of the most important of these factors is the greatly increased significance to present day chemistry of many elements that in the recent past were principally chemical curiosities. Since the Atomic Energy program is concerned with many such elements, it is of interest to discuss the cause for this concern and the resulting effect on the field of … more
Date: October 12, 1953
Creator: Bushey, A. H.
Partner: UNT Libraries Government Documents Department
open access

Proposed alternate dissolving flowsheets for the Redox plant

Description: Current operation of the Redox plant dissolvers results in evolution of ammonia during the slug jacket removal step. Staggering the schedules of the dissolving cycles of the three dissolvers is being practiced at present to prevent the formation of ammonium nitrate crystals in the stack gases, but this procedure limits the dissolver capacity. Steps are being taken to provide ammonia scrubbers for the dissolvers to eliminate this need for close scheduling of dissolving operations. It has been pr… more
Date: August 13, 1954
Creator: Curtis, M. H. & Harmon, M. K.
Partner: UNT Libraries Government Documents Department
open access

Radioactive particles in the 234-5 Building ventilation exhaust

Description: The 234-5 Building ventilation exhaust is continuously sampled for the purpose of estimating the amount of radioactive (alpha emitting) material discharged to the atmosphere. Although a record is kept of the gross amount of radioactive material discharged, few data are available concerning the size and kind of active particles in the exhaust air. Knowledge of the particle size permits: (1) an estimate of the validity of samples drawn through the sampling system, (2) a better knowledge of what t… more
Date: July 13, 1959
Creator: Postma, A. K. & Schwendiman, L. C.
Partner: UNT Libraries Government Documents Department
open access

Physics and Instrument Research and Development Operation. Monthly report, April 1959

Description: Areas covered in this report are as follows: nuclear safety in the Fuel Preparation Dept.; studies related to the present production reactors; studies related to future production reactors; studies related to separation plants; studies form the neutron cross section program; reactor development (gas cooled reactor program and test reactor operations); and biology and medicine.
Date: May 12, 1959
Creator: Gast, P. F.
Partner: UNT Libraries Government Documents Department
open access

Production test IP-2-A: Enriched uranium conversion ratio and stability test

Description: This test as detailed in this report is one of three parts of the initial testing program to demonstrate enriched usage at HAPO. It proposes to irradiate two twelve-tube blocks of enriched uranium and lithium-aluminum slugs to obtain conversion ratios and preliminary information concerning slug stability.
Date: November 12, 1956
Creator: Lang, L. W.
Partner: UNT Libraries Government Documents Department
open access

Historical events of the Chemical Processing Department

Description: The purpose of this report is to summarize and document the significant historical events pertinent to the operation of the Chemical Processing facilities at Hanford. The report covers, in chronological order, the major construction activities and historical events from 1944 to September, 1965. Also included are the production records achieved and a history of the department`s unit cost performance.
Date: November 12, 1965
Creator: Lane, W. A.
Partner: UNT Libraries Government Documents Department
open access

Through reactor decontamination: A technical status report

Description: Attention has focused on the feasibility of conducting through-reactor, internal decontaminations in order to reduce rear face radiation levels and alleviate personnel exposure problems. The purpose of this report is to review the technical aspects of ``through-reactor`` decontaminations and to present an interim recommendation regarding the use of this method.
Date: November 12, 1958
Creator: Miller, N. R. & Hall, R. B.
Partner: UNT Libraries Government Documents Department
open access

Justification for extending scram recovery time at C Reactor

Description: Slug ruptures at C Reactor are costing a considerable amount of production and are limiting reactor power levels. A large portion of this production is lost because the ``quickie`` procedure cannot be used with unstruck ruptures. Currently there are two reasons for this condition: Insufficient reactivity is available to recover after a rupture is removed with the ``quickie`` equipment, and if the ``quickie`` method were attempted, there would be many failures due to stuck rear caps and improper… more
Date: July 13, 1956
Creator: Owsley, G. F.
Partner: UNT Libraries Government Documents Department
Back to Top of Screen