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Chemical Processing Department Monthly Report: June 1965
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.
System:
The UNT Digital Library
Low-temperature hydriding of Zircaloy-2
None
Date:
June 1, 1965
Creator:
Winegardner, W. K. & Richman, R. B.
System:
The UNT Digital Library
Examination of furnace belt failure in 232-Z incinerator
Metallographic examination has been completed on samples from the Nichrome V wire mesh furnace belt in the 232-Z building incinerator. During service the furnace belt had broken in several places where the wire was welded together. A grain boundary phase was found in weld metal during metallographic examination of the as received material. It is probable to conclude that the failure during service was caused by accelerated corrosion of the weld and that the accelerated corrosion in that area was related to the structure of the weld metal. It would be informative to examine welds from the furnace belts that have not failed to further study the cause for the failure.
Date:
February 11, 1965
Creator:
Nelson, T. C.
System:
The UNT Digital Library
Reactor and Materials Technology monthly report, April 1965
This report details activities of the Reactor and Materials Technology Department during the month of April 1965.
Date:
May 14, 1965
Creator:
Albaugh, F. W.
System:
The UNT Digital Library
Quality and availability of fission-products
The information contained in this report was copied from carts used for discussions at Richland on May 4--6, 1965. Representatives of the Martin Company, US Rubber company, General Electric -- HAPO, and AEC-RL00 were present. The data represent the best current information on the quantity, quality, and availability of each fission product considered, i.e., strontium-90, cesium-137, promethium-147, and cerium-144.
Date:
December 31, 1965
Creator:
Rasmussen, M. J.
System:
The UNT Digital Library
Chemical Processing Department Monthly Report: December 1964
This report for December 1964, 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; employee relations; and weapons manufacturing operation.
Date:
January 21, 1965
Creator:
Hanford Atomic Products Operation. Chemical Processing Department.
System:
The UNT Digital Library
Burnout program for high heat flux assemblies
The power of high flux fuel assemblies and three-tube drivers planned for future operations is limited by the burnout safety factor (BOSF). In the past, the power of standard production fuel assemblies was limited almost always by one of the hydraulic limits, and in most cases the assemblies operated at powers significantly below that permitted by the BOSF limit. The burnout conditions for an ``ideal`` fuel surface have been well established in mockups at SRL and Columbia University. Little experimental data are available on nonidealities (such as local hot spots), although calculated factors are applied to the BOSF to account for certain nonidealities. Because of operation at the BOSF limit, better knowledge is needed of the effects of nonidealities and other factors on heat transfer burnout of fuel surfaces. This memorandum presents a program designed to give a better understanding of BOSF.
Date:
May 26, 1965
Creator:
Towell, R. H.
System:
The UNT Digital Library
Radioactive Liquid Waste Disposal for December, 1964
None
Date:
February 17, 1965
Creator:
Wilson, R. H.
System:
The UNT Digital Library
Transfer measurement statistics derived from Purex Processing Measurements` Quality Control Program
The Purex Processing Measurements Quality Control Program was designed to provide for orderly accumulation of measurements data suitable for statistical evaluation and to identify those elements of a measurement which, if improved, would result in significant reduction in overall measurement variation. This report gives an analysis of the audit data obtained at four transfer stations: L9 plutonium product loadout, K6 uranium product to storage, F15 salt waste to F16 and D5 dissolved feed to process. Estimates of variation caused by analytical, sampling and volume or weight instrumentation were computed and combined to give variation associated with a single batch transfer. Procedures for collection of future data that are more suitable for statistical evaluation are suggested. Methods used to compute random and fixed variation estimates are discussed.
Date:
November 23, 1965
Creator:
Hough, C. G.
System:
The UNT Digital Library
K Area Hot Test Hole Temperatures
This report details a K area test with the following objectives: find the temperature range within a graphite sample carrier; find the temperature range with a solid graphite bar; find the temperature range with a test hole; determine the temperature difference between the old and new graphite sample boats; compare the temperature of a sample load and a solid bar in the same location; and find the temperature range in which the graphite samples are irradiated in all test holes. Results and conclusions are presented.
Date:
August 4, 1965
Creator:
Cox, J. H.
System:
The UNT Digital Library
Letter to Mr. Frank Rom, National Aeronautics and Space Administration, Lewis Research Center, Cleveland, Ohio
None
Date:
May 20, 1965
Creator:
Albaugh, F. W.
System:
The UNT Digital Library
River temperature fluctuation problem
None
Date:
February 26, 1965
Creator:
Gustafson, L. D.
System:
The UNT Digital Library
Research and Engineering Operation, Irradiation Processing Department monthly record report, May 1965
Process and development activities reported include: depleted uranium irradiations, thoria irradiation, and hot die sizing. Reactor engineering activities include: brittle fracture of 190-C tanks, increased graphite temperature limits for the F reactor, VSR channel caulking, K reactor downcomer flow, zircaloy hydriding, and ribbed zircaloy process tubes. Reactor physics activities include: thoria irradiations, E-D irradiations, boiling protection with the high speed scanner, and in-core flux monitoring. Radiological engineering activities include: radiation control, classification, radiation occurrences, effluent activity data, and well car shielding. Process standards are listed, along with audits, and fuel failure experience. Operational physics and process physics studies are presented. Lastly, testing activities are detailed.
Date:
June 4, 1965
Creator:
Ambrose, T. W.
System:
The UNT Digital Library
Release of radioactivity to the Columbia River from irradiated fuel element ruptures
McCormack and Schwendiman issued a report in 1959 which estimated the amount of fission products from fuel element failures entering the Columbia River during the period 1952--1958 inclusive. Since that time there have been no attempts made to publish similar information for the subsequent years. It is the purpose of this report to review the fuel element rupture experience of 1964 as somewhat typical of the last few years, and to estimate the amount of significant fission products which entered the Columbia River. The routine measurements of fission products both in the reactor effluent streams and in the Columbia River will be reviewed for comparison purposes.
Date:
May 27, 1965
Creator:
Jerman, P. C.; Koop, W. N. & Owen, F. E.
System:
The UNT Digital Library
Horizontal distortion measurements, C Reactor
None
Date:
March 24, 1965
Creator:
DeMers, A. E.
System:
The UNT Digital Library
N-Reactor Department research and development budget for FY-1967 and revision of budget for FY-1966
This report provides the N-Reactor research and development budget for fiscal year 1967 and modifications of the budget for fiscal year 1966.
Date:
April 19, 1965
Creator:
unknown
System:
The UNT Digital Library
Conversion ratio tables
This manual provides a list of the quantities of plutonium and plutonium isotope formation. Other isotopes whose concentrations are important and included in this report are U-236 buildup, U-235 burnout, U burnout, Np-237 build-up, GVR (the Gas Volume Ratio) in coproduct target elements and equivalent gram of plutonium. These conversion tables have been calculated on the IBM 7090 digital computer using a program entitled ``FLEX-3.`` The results of the computer solutions have not been normalized to conversion observed by Chemical Processing Department measurement since none are yet available. Conversion ratios for four types of N-Reactor fuel have been evaluated, they are: (1).947 percent U-235 normal fuel loading; (2)1.25 percent U-235 ``spike`` enrichment; (3)1.25 percent U-235 outer, Li-Al inner -- coproduct fuel; (4)1.96 percent U-235 outer, Li-Al inner -- coproduct fuel.
Date:
July 2, 1965
Creator:
Chitwood, R. A.
System:
The UNT Digital Library
Vertical bowing measurements: B Reactor, tube 1575
None
Date:
September 15, 1965
Creator:
DeMers, A. E.
System:
The UNT Digital Library
Irradiation Processing Department monthly research and development report, August 1965
This research and development report details activities of the Irradiation Processing Department during the month of August 1965.
Date:
September 3, 1965
Creator:
Ambrose, T. W.
System:
The UNT Digital Library
N-Fuels Engineering programs: CY-1965
Programs undertaken by N-Fuels Engineering should be designed to achieve the following general objectives; (1) maintain and/or improve fuel element quality level necessary to assure satisfactory reactor performance; (2) develop the fuel fabrication technology required to support the development and testing of new fuel designs; (3) reduce fuel manufacturing costs to achieve projected operated cost targets; (4) reduce the uranium metal costs charged to N-Reactor. Further, these programs must be integrated to provide maximum support to identifiable Section and Department goals. The specific goals for CY-65 are: (1) development technology necessary to support conversion to co-product operation early in CY-66; (2) conduct a program of uranium fabrication development to improve fuel element quality and reduce uranium costs; (3) improve fuel element quality, manufacturing yields, and conversion costs for the current production fuel design; (4) develop fuels capable of extended exposure and/or higher power level operation in support of alternate reactor operating plans; (5) develop new fuel fabrication techniques to extend the capabilities for fuel fabrication within the N-Reactor Department; (6) initiate equipment design and procurement actions as necessary to provide capability to meet production schedules.
Date:
January 8, 1965
Creator:
Nickolaus, J. W.
System:
The UNT Digital Library
Status of plant assistance irradiations as of April 9, 1965
This report covers the activities with regard to on-site customer irradiations as of the above date. The report covers the status of material undergoing irradiation awaiting dispositions material shipped during the months and current status of all reactor test holes. The integrated exposure values are calculated in accordance with HW-62781, ``Status Report Equations.`` The integrated exposure reported is the average exposure received by the surrounding uranium columns. Conversion to exposure received by the sample is left to the customer.
Date:
April 23, 1965
Creator:
Ferguson, J. H.
System:
The UNT Digital Library
Analysis of PT-684-A hot die size process parameters evaluation
None
Date:
February 4, 1965
Creator:
unknown
System:
The UNT Digital Library
Vertical bowing measurements, F Reactor
None
Date:
July 2, 1965
Creator:
DeMers, A. E.
System:
The UNT Digital Library
Tritium extraction facility study - 1965
This study was prepared in support of AEC-requested reactor case studies. Two of the cases include local separation and purification of tritium from Hanford irradiated aluminum-lithium alloyed slugs after 1974, at which time, the Savannah River Plant would be shut down. Consideration is given to processing N Reactor rods or {open_quotes}K{close_quotes} Reactor I&E slugs. Quantities of tritium to be produced would be five kilograms per year in one case and seven kilograms per year in the other case. The facility would process tritium only through the purification stage. At this point the material would be shipped offsite for storage, packaging and any future weapon stockpile rework.
Date:
August 20, 1965
Creator:
Kesel, G. P. & Wodrich, D. D.
System:
The UNT Digital Library