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Culture of oats in the western states.

Description: Describes the different areas of the United States where oats are grown, how to prepare the soil, and how to effectively plant and harvest oats.
Date: June 1959
Creator: Coffman, Franklin A. (Franklin Arthur), 1892-; Stevens, Harland, 1907- & Stanton, T. R. (Thomas Ray), b. 1885
Item Type: Refine your search to only Book
Partner: UNT Libraries Government Documents Department
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Preliminary Studies of Scavenging Systems Related to Radioactive Fallout : Seventh Letter Report, April 1 to May 31, 1959

Description: Introduction: "This is the seventh letter report on ARF Project C 127, entitled "Preliminary Studies of Scavenging Systems Related to Radioactive Fallout." This report covers the period from April 1 to May 31, 1959."
Date: June 15, 1959
Creator: Stockham, John D. & Rosinski, John
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Investigation of Graphite Bodies : Progress Report No. 3 for the Period March 1, 1959 to May 31, 1959

Description: This document is the third in a series of progress report that records investigations of graphite bodies. Along with the report, two appendices are given to describe the different graphite bodies: "Synthetic Binders for Carbon and Graphite" and "High Temperature Physical Properties of Molded Graphites".
Date: June 10, 1959
Creator: Bradstreet, Samuel W.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Radiation Shielding for Test Cell "C"

Description: "This report contains information on the following topics related to the radiation shielding at test cell "C". (1) Calculation of wall and roof thicknesses. (2) Calculation of radiation heating of front wall by gamma and neutron absorption. (3) Calculation of neutron activation in front face of test cell. (4) Calculation of γ-dose rates both direct and behind shadow shields at various distances. (5) Dose produced by a reactor catastrophe."
Date: June 1959
Creator: Fenstermacher, Charles Alvin & Henshall, James
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Proceedings of the Sixth Tripartite Instrumentation Conference, Part 3: System and Component Reliability

Description: Collection of papers presented during the third session (Tuesday, April 21, 1959) at the 6th Tripartite Instrumentation Conference. The five papers describe reliability, maintenance, and failure of electronic equipment and other components in reactors at Chalk River (Canada), Harwell (U.K.), and Oak Ridge (U.S.).
Date: June 1959
Creator: Woolston, J. E. & Townsend, S. J.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Existing reactor expansion study basis

Description: The latest HAPO Five Year Program review, HW-59633, forecasts substantial increases in Pu production from the eight existing Hanford reactors over the next several years. These production increases would be attained by a combination of several methods which include increased reactor power levels resulting from higher process water flow rates and coolant bulk outlet temperatures, improved time operated efficiency, higher conversion ratios, and reduced transient reactivity losses. In order to pro… more
Date: June 24, 1959
Creator: Heacock, H. W.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Radiometallurgical examination of PT-IP-221-A measurement of flow channel temperature in 7 rod cluster fuel element (RM-287)

Description: Eight Zircaloy-2 jacketed, natural uranium seven-rod cluster elements were irradiated in a KER loop to determine flow channel temperature characteristics. One of the elements, which had 200 MWD/T exposure, was sent to the Radiometallurgy Laboratory for examination in April 1959. An outside rod of the cluster was sectioned and examined metallographically. No cracks or flaws were observed in the uranium cladding or bonding.
Date: June 16, 1959
Creator: Teats, R.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Technical basis for establishing process tube pressure limits for KER loops 2 and 3 and for the NPR Prototype Facility

Description: In compliance with a request from Coolant Testing Operation, the Reactor Engineering Operation has made a study to determine the maximum operating pressure limits for the pertinent Zircaloy-2 process tubes. Since these tubes shall be used for testing NPR fuel elements, it is considered desirable that KER Loops 2 and 3 permit operation at temperatures of around 300{degrees}C while the NPR prototype facility permit operation at about 316{degrees}C in a manner such that there is minimum hazard to … more
Date: June 26, 1959
Creator: Adams, O. E.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Hanford Laboratories Operation Monthly Activities Report: May 1959

Description: This is the monthly report for the Hanford Laboratories Operation, May, 1959. Reactor fuels, chemistry, dosimetry, separation processes, reactor technology, financial activities, biology operation, physics and instrumentation research, employee relations, operations research and synthesis operation, programming, radiation protection, and laboratory auxiliaries operation area discussed.
Date: June 15, 1959
Creator: Hanford Laboratories
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Irradiation performance of enriched uranium clad in stainless steel: PT-IP-123-A. Final report

Description: Early in the development of an extended surface fuel element for use in the NPR, several 7-rod cluster fuel elements were irradiated to determine the dimensional stability of such geometries at high burnups. These elements were fabricated from small diameter uranium rods clad unbonded in stainless steel tubes and assembled in a rod cluster geometry by various support devices. Zircaloy clad fuel rods were not yet available, the stainless steel clad rods therefore served as a suitable material wh… more
Date: June 9, 1959
Creator: Claudson, T. T.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Neutron flux in K Reactor discharge area during operation

Description: Based on the activation of gold foils in an hydrogeneous medium, the neutron flux incident on the rear wall of the discharge area of the KE reactor is estimated to be 6000 M/cm{sup 2} sec. The effective energy of the neutrons is estimated to be approximately 4 Mev. Neither of these values confirm order-of-magnitude estimates of the neutron flux and neutron energy expected to exist in the discharge area.
Date: June 19, 1959
Creator: Bunch, W. L.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Revised recommendations for the 100-K Area Project CG-775 raw water requirements

Description: As a part of Project CG-775, 100-K Area Water Plant Expansion, the capacity of the 181-K river pump installations will be increased. Recommendations for the raw water requirements based on a reactor flow of 175,000 gpm were presented in document HW-55877. Since then a new fuel element has been developed for the K reactors, resulting in a lower reactor system curve. It is recommended that the design criteria for the 181-K river pumps be based on a total raw water flow of 213,000 gpm with spare p… more
Date: June 22, 1959
Creator: Fifer, N. F.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Comments on calcined 1WW storage

Description: Studies are under ray in Chemical Research and Development to-provide the technical ``know-how`` necessary to calcine Purex 1WW and safely store the solid product. The solid product can be stored as the particulate solid from the calciner or, after further treatment, as a solid matrix or melt. In this regard, Chemical Research is studying a PO{sub 4}BO{sub 2} melt. This document presents expected fission product heat generation rates in the solid product, shows the effect of various variables o… more
Date: June 3, 1959
Creator: Coppinger, E. A.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Supplement C -- Production test IP-64-CE poison column displacement during reactor operation

Description: The objectives of this supplement are to test an improved prototypic slug column displacement winch and associated remote control equipment and to demonstrate the feasibility of exerting control over the front-to-rear neutron flux changes as an aid in controlling reactivity cycling. An array of poison displacement columns up to twelve in number is intended, each charge consisting of a center section of I and E natural uranium slugs with mint pieces on each end. Initially six such columns will b… more
Date: June 16, 1959
Creator: Hedges, J. W. & Carter, R. D.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Production test IP-250-A irradiation of Zircaloy-2 jacketed tube-and-tube elements in the KER loops

Description: This report discusses testing three-foot Zircaloy-2 jacketed tube-and-tube elements with either natural or 1.6% enriched unalloyed or 2% zirconium alloyed uranium which will be irradiated in any of the KER Loops to goals up to 5000 WD/T. Downstream thermocouples to measure flow channel coolant temperatures will be included for charges of enriched elements. Special tray discharges to prevent the fall of the elements to the basin are required for all loadings. The tube-and-tube geometry is being … more
Date: June 1, 1959
Creator: Kratzer, W. K.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Relative Ball 3X-VSR reactivity strength DR reactor. Interim Report of PT IP-126-C

Description: Prior to this experiment, no measurements of Ball 3X effectiveness had been performed for any of the older 2004-tube Hanford piles, and calculations concerning total control requirements were made assuming the vertical safety system strength equal to the strength of the B, D, F vertical safety rods. With current and projected enrichment loadings, the vertical control system was calculated to be inadequate to satisfy the total control criteria at all times, resulting in the necessity to provide … more
Date: June 1, 1959
Creator: Simpson, D. E.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

K Reactor panellit protection against plugging incidents with low front header pressure

Description: The purpose of this report is to present the results of experimental tests made to determine the degree of protection offered by the Panellit system to accidental flow reductions caused by plugging incidents to a K reactor process tube operating at low front header pressures.
Date: June 1, 1959
Creator: Fitzsimmons, D. E. & Hesson, G. M.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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The Palmolive cycle at Hanford

Description: The Palmolive program is directed toward the recovery of neptunium-237 and production of plutonium-238. The neptunium is recovered during the chemical processing of irradiated uranium and is purified and fabricated into target elements. The target elements are irradiated to produce plutonium-238 by neutron capture of neptunium-237 and are processed to provide plutonium for shipment to the final customer and neptunium for recycle within the system. The following report summarizes a preliminary e… more
Date: June 24, 1959
Creator: Judson, B. F. & Beard, S. J.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Proposed study program of the effects on Hanford of a dam at Columbia River mile 348

Description: At the request of Hanford Operations Office, Atomic Energy Commission, a study was made of the effects on the Hanford Facilities of a navigation and power dam at Columbia River mile 348, about five miles upstream of the 300 Area. The original study was based on a nominal slack-water pool elevation of 395 to 400 feet at the dam location. A supplemental study evaluated the effects on plant facilities of a dam at the same location but with slack-water pool elevation of 385 feet. In addition to eff… more
Date: June 30, 1959
Creator: Jasko, R. T.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Gamma energy analysis of the RMA Line and Recuplex

Description: Knowledge has developed steadily over the past 18 months toward defining the characteristics of the gamma and neutron radiation associated with plutonium and its compounds. Laboratory measurement have been made on plutonium samples taken from the RMA Line, film badge studies have been made in plutonium processing areas, and calculations have been made predicting dose rates and shielding requirements at higher plutonium exposure levels. As these studies continue, and more precise data is accumul… more
Date: June 15, 1959
Creator: Brown, C. L.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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