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in publisher: "Hanford Atomic Products Operation"  
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OXIDATION OF GRAPHITE UNDER HIGH TEMPERATURE REACTOR CONDITIONS

Description: A kinetic study was conducted to provide information on oxidation of reactor graphites in the temperature range of 450 to 675 deg C and on the effects of reactor environment on oxidation rates. Among the parameters studied were chemical reactivity of the graphite, prior oxidation, a high intensity gamma flux during oxidation, variation of the surface-to-volume ratio of the graphite specimens, neutron bombardment prior to oxidation exposure, and gas flow rates. Rate equations showed apparent act… more
Date: July 1, 1961
Creator: Dahl, R.E.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Use Test Comparison of TBP Diluents

Description: Several diluents for possible use in TBP Purex Plant solvent were tested. The tests included nitric --nitrous acid degradation, fission prcduct distribution under simulated plant conditions, emulsillcation, and radiolysis. The order of quality of four diluents is n-dcdecane> Soltrol 170> Shell Code 85030(82000)> Shell E-2342. (D.L.C.)
Date: July 1, 1961
Creator: Mendel, J. E.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Disposal of irradiated waste Ink'' solution (Production Test 105-529-A)

Description: Boron solution circulated through special poison tubes to achieve more variable control of neutron flattening'' was tested in the 100-DR Hanford reactor. About 2700 gallons of irradiated waste Ink solution from Production Test 105-529-A was discharged to an underground crib at 100-DR, after radiochemical analyses and evaluation of radiation protection aspects by the Radiological Sciences Department. In case the Ink method is considered for production use at Hanford in the future, further biolog… more
Date: July 20, 1954
Creator: Clukey, H. V.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Irradiation Processing Department monthly report, June 1962

Description: This document details activities of the Irradiation Processing Department during the month of June, 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: July 13, 1992
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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The use of ALUM and activated silica for 100 Area process water coagulation. Final report

Description: Production rates of the Hanford reactors can be increased in proportion to the quantity of process cooling water which can be supplied to them. This water must be of such a quality that slug and tube corrosion rates are acceptable, the gross activity of the effluent water must not be excessive, the concentration of specific radioactive isotopes constituting a radiological hazard must be minimized, and the film formation rates should be as low as possible. In the Hanford water treatment process,… more
Date: July 15, 1955
Creator: Woods, W. C. A.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Irradiation Processing Department monthly report, June 1963

Description: This document details activities of the irradiation processing department during the month of June, 1963. 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 Financial Operation.
Date: July 15, 1963
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Irradiation Processing Department monthly report, June 1964

Description: This document details activities of the Irradiation Processing Department during the month of June, 1964. 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; Employee Relations Operation; and Financial Operation.
Date: July 15, 1964
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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An Introduction to the Purex Plant

Description: The intent of this manual is to present a description of the main process building, equipment, and auxiliary facilities as well as a process summary. Material is of a scope nature with more detail devoted to features unlike those of existing separations systems. An attempt is made to convey some of the basic design philosophy and the problems encountered in the development of design criteria. This information is written primarily for Separations Section supervision who have not had an opportuni… more
Date: July 15, 1954
Creator: Courtney, J. J. & Clark, B. E., Jr.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Chemical Processing Department Monthly Report: June 1963

Description: This report, from the Chemical Processing Department at HAPO for June 1963, discusses the following: Production operation; Purex and Redox operation; Finished products operation; maintenance; Financial operations, facilities engineering; research; and employee relations; weapons manufacturing operation; and power and crafts operation.
Date: July 22, 1963
Creator: Hanford Atomic Products Operation. Chemical Processing Department.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Production test IP-285-C and supplement a measurement of operating temperatures of uncooled thermal shield cooling tube. Final report

Description: The iron thermal shields of the Hanford reactors are cooled by means of water flow through thermal cooling tubes embedded in the shield blocks. The flow rate, temperature rise, and allowable pressure in the tubes and the conditions under which some of the tubes may be out of service are specified in the process standards. Shield heat formation and heat transfer calculations are necessarily based on broad assumptions and are therefore usually reliable only for order of magnitude and trend predic… more
Date: July 20, 1960
Creator: Smalley, W. L.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Chemical Processing Department Monthly Report: June 1965

Description: This report, for June 1965 from the chemical Processing Department at HAPO, discusses the following: Production operation; Purex and Redox operation; Finished products operation; maintenance; Financial operations; facilities engineering; research; and employee relations.
Date: July 21, 1965
Creator: Hanford Atomic Products Operation. Chemical Processing Department.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Stress Analysis of Bulk Effluent System Components in B and C Reactors

Description: This report presents a study of the stresses induced in the elbow and downcomer of the B and C Reactors (bulk effluent systems) by flow momentum and pressurization effects. It is desirable to ascertain the limitations on the bulk outlet temperatures and flow rates from a stress viewpoint; the elbow, top coverplate of downcomer, and top baffle plate being the most severely stressed components.
Date: July 10, 1958
Creator: Adams, O. E., Jr.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Testing of Zircaloy-2-Clad Uranium Seven-Rod Fuel Elements. Final Report

Description: In 1955 the Fuels Development Operation began irradiation testing of fuel elements in high temperature water. It was assumed that if a new reactor were built at Hanford, it would be cooled by high-temperature, pressurized water. Corrosion tests showed that aluminum-clad production fuel elements could not be used in high-temperature water. Therefore, while work to improve the resistance of aluminum to high-temperature water proceeded, the Fuel Design Operation began irradiation of stainless stee… more
Date: July 5, 1960
Creator: Geering, G. T.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Final report on production test IP-289-I, Supplement 1, H reactor export flow test

Description: The raw water export system forms the last ditch water supply system to the ``O`` and ``C`` type reactors; in the event of electrical and steam power failure, the export system is designed to supply enough raw water coolant. After the original export orifice was modified twice, the export system was retested.
Date: July 10, 1961
Creator: Cremer, B. R.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Production test IP-603-I evaluation of accidental fuel flushing potential D-DR reactors

Description: This purpose of this test is to acquire data to support further studies aimed at determining whether a normal column of I&E enriched fuel elements or a normal column of natural fuel elements can be flushed from a process tube with the crossheader valved down to shutdown position if the front riser pressure is raised to normal operation pressure.
Date: July 30, 1963
Creator: Hollifield, P. J. & George, D. K.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Pilot-plant studies of mercury-catalyzed dissolving of aluminum-jacketed fuel elements

Description: The objective of the experimental studies reported herein was to demonstrate the laboratory-developed mercury-catalyzed dissolving procedure on a pilot-plant scale by conducting a series of test dissolutions of aluminum-jacketed, unirradiated uranium in the 150-gallon downdraft type semiworks dissolver in 321 Building. It was desired to establish: (1) the effect of the larger-scale operation on time cycle; (2) dissolution rates of aluminum and uranium, (3) controllability of the reactions, and … more
Date: July 1, 1954
Creator: Bradford, J. L. & Adler, K. L.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Hanford Laboratories monthly activities report, June 1963

Description: This is the monthly report for the Hanford Laboratories Operation, June 1963. Metallurgy, reactor fuels, chemistry, dosimetry, separation processes, reactor technology, financial activities, visits, biology operation, physics and instrumentation research, and employee relations are discussed.
Date: July 15, 1963
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Longitudinal flux flattening

Description: To date a great deal of emphasis has been placed on flattening the side-to-side and top-to-bottom flux distribution with only minor effort to improve the front-to-rear distribution. Minor variations in the front-to-rear distribution have been achieved by horizontal control rod and Supplemental control positioning. It has-been reasonably well established that the rupture potential for one tube charge increases markedly with higher specific power and temperature; thus there is a great deal of inc… more
Date: July 19, 1960
Creator: Stiede, W. L.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Evaluation of the ``machined parts`` cask for off-site shipments of irradiated lithium

Description: The ``machined parts`` casks are shipped to Hanford by Savannah River for loading with irradiated lithium alloy slugs and returned for processing. The casks have been in service for about 10 years and have shielding material more than what is required by regulations for radiation attenuation. Evaluation shows that rupture of the shell is probable for edge or corner drop, with considerable displacement of shielding. The cask would fail in a 2-hour fire of 2000 F with loss of shielding and probab… more
Date: July 12, 1963
Creator: Peck, G. E.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

The processing of Pu scrap at Hanford

Description: This study responds to the requests for data on the subject contained in the D.S. Burrows letter entitled ``Processing Plutonium Scrap`` (symbol FAc:EAS) dated June 30, 1961 and received for reading by Chemical Processing Department Management on July 5, 1961. Cognizance is also taken of the July 5 teletype from G.F. Quinn requesting an appendix updating the content of our document HW-63560 (Pu Reclamation -- January 18, 1960) with regard to safety aspects covered therein. Appendix A of this pa… more
Date: July 13, 1961
Creator: Grimm, K. G.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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