48 Matching Results

Search Results

Results: 1 - 24 next
open access

Stress Corrosion Cracking in Uranium-Molybdenum Alloys

Description: Investigation conducted to determine the cause of cracking, during tension, on the surface of tensile specimens of uranium-molybdenum alloys.
Date: August 12, 1963
Creator: Pridgeon, J. W.
Partner: UNT Libraries Government Documents Department
open access

The Design Study of Fluid Engine Power Systems

Description: From abstract: This report presents information generated during a six month feasibility study of an engine which uses a supercritical working fluid as the secondary portion of nuclear powered electric generating system.
Date: April 12, 1963
Creator: Baker, C. H.; Hunter, T. A.; Pauliukonis, R. S. & Pradhan, A. V.
Partner: UNT Libraries Government Documents Department
open access

Radioactive contamination in liquid wastes discharged to ground at the separations facilities through December 1962

Description: This document summarizes the amounts of radioactive contamination discharged to ground from separations facilities through December 1962. Detailed data for individual disposal sites are presented on a month-to-month basis for the period of January through December 1962. Previous publications of this series are listed in the bibliography and may be referred to for specific information on measurements and radioactivity totals prior to December 1962. Tables list the major disposal sites in the sep… more
Date: March 12, 1963
Creator: Backman, G. E.
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.
Partner: UNT Libraries Government Documents Department
open access

Suggested startup plan with high CO{sub 2}

Description: Following the startup of 11-6-63 at 105-B, there was an operating period where graphite stringer temperatures were above allowable, and a PCA was authorized for continued operation. It is probable that the combined effects of raising the CO{sub 2} rapidly along with the fast approach to full power level caused the temperature effects. The CO{sub 2} reached 67%. As an interim step, it is suggested that startup CO{sub 2} additions be tailored to level off at 5--10% below the equilibrium level, an… more
Date: November 12, 1963
Creator: Gross, P. D.
Partner: UNT Libraries Government Documents Department
open access

Supplement A to PT-IP-572-A effect of eccentricity on the irradiation behavior of KVNS fuel elements

Description: With the use of smooth-bore Zircaloy-2 process tubes and self- supported fuel elements on a large scale at the K Reactors, establishment of the operating characteristics of this fuel element-process tube configuration is imperative. Under authority of Production Test-IP-409-A, two smooth-bore Zircaloy-2 tubes were routinely charged with KVNS fuel elements. Approximately 520 KVNS fuel elements have been irradiated in this facility. In Production Test-IP-572-A, the coolant temperature distributio… more
Date: April 12, 1963
Creator: Carlson, P. A. & Hladek, K. L.
Partner: UNT Libraries Government Documents Department
open access

Production test IP-582-D, Irradiation of depleted uranium in the KW Snout Facilities, HAPO-275

Description: The objective of this test is to produce 50 milligrams of neptunium 239 for a process stream study in the Purex plant. The efficient recovery of neptunium 237 as an alternate product produced at HAPO is presently impaired by the lack of knowledge of the distribution of neptunium 237 in the several Purex process streams. Present methods of following the neptunium 237 through the process streams involves inadequate alpha counting techniques. However, neptunium 239, because of its discrete gamma d… more
Date: April 12, 1963
Creator: Cox, J. H.
Partner: UNT Libraries Government Documents Department
open access

Emergency storage basin coolant: Design criteria for architect-engineer usage

Description: This document defines the objectives, bases, and functional requirements that shall govern the preparation of detail design of the gravity fed water supply to reactor storage basins for all eight reactors. In the event that appears advisable and feasible to discharge all metal from the reactors into the metal storage basins, it would be necessary to add water to the storage basins to prevent overheating of the fuel elements. Without the addition of cool water the storage basin water would soon … more
Date: September 12, 1963
Creator: Brinkman, L. B.
Partner: UNT Libraries Government Documents Department
open access

Evaluation of the B-cask in accordance with proposed regulations of the AEC and ICC for off-site shipments of irradiated bismuth

Description: The growing concern of government agencies for safe shipment of radioactive materials, both in this country and in Europe, has resulted in a number of proposed regulations governing every phase of shipment including the design of the cask or container, There have been requests during the last year for increased shipments of irradiated bismuth from Hanford. This radioactive material has been shipped in the B-cask to the off-site processing plant for several years. These two factors, proposed reg… more
Date: July 12, 1963
Creator: Peck, G. E.
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

Corrosion of Zircaloy-2 by pH 10 LiOH in heated crevices

Description: Both the inner and outer tubes of the N-Reactor fuel elements will have self supports spot welded to the lateral heat-transfer surface of the element. A crevice a few mils thick will exist around the weld between the support tab and the cladding. Because of the heat flux through the cladding at this point and the insulating effect of the support tab, the temperature in this crevice will be higher than that on the free surface away from the support. This can result in boiling in the crevice lead… more
Date: November 12, 1963
Creator: Dickinson, D. R.
Partner: UNT Libraries Government Documents Department
open access

Pressure measurements on 19-1/2 crossheader: DR Reactor

Description: Equipment Laboratory and Testing Operation was requested to measure the pressure gradient developed across a nozzle and crossheader assembly used on the rear face during reactor operation. A nozzle and pigtail assembly with pressure taps was installed on process tube 2058, and pressure taps were located at the center, at tube 2058, and at the end of crossheader No. 19-1/2. copper sensing lines were installed between the pressure tape and a tool storage area on zero level, near side of the react… more
Date: June 12, 1963
Creator: Rand, J. L.
Partner: UNT Libraries Government Documents Department
open access

630A Maritime Nuclear Steam Generator: Status Report Number 1

Description: From foreword: The primary purpose of this document is to set forth the current status of the 630A Nuclear Steam Generator, under development for the U.S. AEC.
Date: September 12, 1963
Creator: General Electric Company. Nuclear Materials and Propulsion Operation.
Partner: UNT Libraries Government Documents Department
open access

SELF-LIMITING EXCURSION TESTS OF A HIGHLY ENRICHED PLATE-TYPE D$sub 2$O- MODERATED REACTOR. PART I. INITIAL TEST SERIES

Description: Self-limiting power excursion tests were made to investigate the dynamic response of the Spert II BD-22/24 expanded D/sub 2/O core. This D/sub 2/O- moderated core is comprised of 3-in.-square x 24-in.-long, highly enriched, uranium-aluminum, plate-type fuel assemblies spaced on 6-in. centers. The power excursions were initiated by stepwise reactivity insertions with the system at ambient temperature and atmospheric pressure, with no forced coolant flow, and with approximately a 50-in. D/sub 2/O… more
Date: July 12, 1963
Creator: Grund, J.E.
Partner: UNT Libraries Government Documents Department
open access

BEVATRON OPERATION AND DEVELOPMENT. XXXIII. Period Covered February- April 1962

Description: Experimental work consisted of one new run started and completed this quarter, and the completion of one of the three continuing runs. Of the scheduled operating time, the beam was on for 69.4% of the time, 2.3% of the time was used for experimental setup, and equipment outage took 29.3% of the time. There were two scheduled and two impromptu shutdowns. During one of the scheduled shutdowns the external-beam extraction magnets were installed in the east and south tangent tanks. The other schedu… more
Date: February 12, 1963
Creator: Crebbin, K.C.; Wenzel, W.A.; Lothrop, F.H.G. & Johnson, R.M.
Partner: UNT Libraries Government Documents Department
open access

Preliminary Solution Critical Experiments for the High-Flux Isotope Reactor

Description: The design of the High-Flux Isotope Reactor (HFIR) was supported by a series of preliminary experiments performed at the Oak Ridge Critical Experiments Facility in 1960. The experiments yielded results describing directly some of the expected performance characteristics of the reactor and strengthened the calculational methods used in its design. The critical assembly, like the reactor, was of a flux-trap type in which a central 6-in.-dia column of H/sub 2/O was surrounded by an annulus of fiss… more
Date: June 12, 1963
Creator: Fox, J. K.; Gilley, L. W. & Magnuson, D. W.
Partner: UNT Libraries Government Documents Department
open access

Stress Corrosion Cracking in Uranium-Molybdenum Alloys

Description: An investigation was conducted to determine the cause of cracking, during tension, on the surface of tensile specimens of U--Mo alloys. The cracking was observed in alloys that were water quenched from a temperature range in which the body-centered cubic gamma phase was stable and, subsequently, stressed in tension. The investigation was carried out on alloys of U--Mo containing 5 and 4 wt% Mo. It was discovered early in the study that the cracking could be eliminated by testing tensile specime… more
Date: August 12, 1963
Creator: Pridgeon, J. W.
Partner: UNT Libraries Government Documents Department
open access

Pathfinder Atomic Power Plant. Clustered Pin Superheater Lattice Experiments

Description: Experiments to obtain detailed thermal flux distribution measurements within a unit fuel cell and measurements of sub-cadmium and epi-cadmium U/sup 238/ absorption in the fuel rods are described. These quantities are required for determination of the thermal utilization and resonance escape probability of the fuel loading. (auth)
Date: February 12, 1963
Creator: Selep, A.
Partner: UNT Libraries Government Documents Department
open access

Irradiation Processing Department monthly report, March 1963

Description: This document details activities of the Irradiation Processing Department during the month of August, 1958. 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: April 12, 1963
Partner: UNT Libraries Government Documents Department
Back to Top of Screen