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Decomposition of Water at High Temperatures and Pressures Under Reactor Irradiation

Description: Partial abstract: "The investigation of the high temperature and pressure dissociation of water under irradiation was undertaken by the Power Pile Division of Oak Ridge National Laboratory in an effort to determine the degree of importance of the phenomenon with respect to the design of a high temperature water-cooled power reactor. Theory and past experimentation indicate that net steady-state dissociation is determined by the rates of the dissociation and recombination reactions under the imposed conditions, the dissociation rate being essentially a function of flux and the recombination rate essentially a function of temperature" (p. 3).
Date: September 16, 1949
Creator: Fromm, L. W.
Partner: UNT Libraries Government Documents Department

PM-1 Reactor Core Final Design Report

Description: From introduction: This report presents and evaluates the final design of the reactor core for the PM-1 Nuclear Power Plant. The design criteria required a pressurized water cooled and moderated core with a two-year life at design power and a positive shutdown margin under all conditions with either one control rod stuck completely out or with two control rods stuck in the operating condition.
Date: January 1962
Creator: Bagley, R. O.; Cox, F. H.; Carnasale, A. & Vener, H.
Partner: UNT Libraries Government Documents Department

Plutonium Recycle Test Reactor Final Safeguard Analysis: Supplement 2, Consequences of a Primary Coolant Leak

Description: Review of previous work is presented in addition to the results of recent studies concerning loss of primary coolant when the system is cold and pressurized and the problem of supplying adequate cooling following the injection of light water.
Date: November 15, 1960
Creator: Wittenbrock, N. G.
Partner: UNT Libraries Government Documents Department

Survey of Piping Failures for the Reactor Primary Coolant Pipe Rupture Study

Description: From summary: "An industrial piping failure survey covering 701 contacts in electric utilities, petroleum refineries, chemical processing, marine applications, architect-engineers, component manufacturers, piping fabricating and erectors, insurance companies, and others was conducted as part of the Reactor Primary Coolant Rupture Study."
Date: May 1964
Creator: U.S. Atomic Energy Commission
Partner: UNT Libraries Government Documents Department

A Recirculating Supercritical Water Loop

Description: From abstract: "A recirculating high-pressure stainless steel loop was developed for the study of heat transfer from small-bore tubes to supercritical water. It was found that under certain conditions, hot spots developed on the test section. The conditions leading to the formation of hot spots were investigated; the results of several runs are tabulated here."
Date: October 25, 1954
Creator: Epstein, H. M.; Goldthwaite, W. H.; Chastain, Joel W. & Fawcett, Sherwood L.
Partner: UNT Libraries Government Documents Department

A Recirculating Supercritical Water Loop

Description: From Abstract: "A recirculating high-pressure stainless steel loop was developed for the study of heat transfer from small-bore tubes to supercritical water. It was found that under certain conditions, hot spots developed on the test section. The conditions leading to the formation of hot spots were investigated; the results of several runs are tabulated here."
Date: October 25, 1954
Creator: Epstein, H. M.; Goldthwaite, W. H.; Chastain, Joel W. & Fawcett, Sherwood L.
Partner: UNT Libraries Government Documents Department

The Fabrication of Subassemblies for the Supercritical-Water Reactor

Description: In studies of the fabrication of fuel subassemblies for the supercritical-water reactor, the limited ductility of stainless steel-UO₂ fuel sheet made the fabrication of corrugated-flat-plate-type subassemblies impractical. A fabricable MTR-type assembly, 5/8 in. square and 30 in. long, was developed. Methods for edge cladding fuel sheet were developed and a brazing alloy, GE-75, was found to be corrosion resistant in supercritical water.
Date: August 16, 1954
Creator: Keeler, J. R. & Hare, Alan W.
Partner: UNT Libraries Government Documents Department

Centrifugal Casting of Aluminum-Uranium Alloys

Description: "Centrifugal-casting techniques were investigated as a method of producing hollow cylindrical extrusion billets of aluminum-35 w/o uranium. Among the variables evaluated were melt temperature, mold and pouring-spout configurations, mold speed, and method of pouring. With the equipment employed it was found that the best castings were produced stilizing a pouring temperature of 2400 F, a heavy-walled steel cylinder rotating between 700 to 900 rpm for the mold and bottom-pouring technique employing a retractable pouring spout. Sound, nonporous billets 26 in. long and 5 in. in diameter were produced with a yield after machining of over 75 per cent of the original charge. The major losses occurred in the pouring spout-and-cup assembly. This loss is relatively unaffected by the casting length; and, therefore, coatings of greater length than 26 in. should results in even greater recoveries.
Date: July 20, 1959
Creator: Daniel, Norman E.; Foster, Ellis L. & Dickerson, Ronald F.
Partner: UNT Libraries Government Documents Department

Criticality research in support of chemical reprocessing in the Thorium Fuel Cycle Technology Program: basic process description

Description: The basis processes for reprocessing thorium based light water reactor type fuels are defined for use in identifying criticality data needs. The Reference Thorium Fuel Cycle is used as the primary fuel cycle. Material forms and compositions are described for each major processing step. These forms consist of nitrates and oxides of Th--U--Pu combinations. Fuel fabrication and fuel pool storage facilities are also defined to the extent they interact with fuel reprocessing.
Date: May 1978
Creator: Libby, R. A.
Partner: UNT Libraries Government Documents Department

Light-Water-Reactor Safety Research Program

Description: Report of a long-term program for monitoring the irradiation behavior of the materials in service in the primary-system sodium and the neutron shield of the EBR-11 sodium-cooled fast breeder reactor.
Date: 1977?
Creator: Argonne National Laboratory
Partner: UNT Libraries Government Documents Department

Light-Water-Reactor Safety Research Program

Description: This progress report summarizes the Argonne National Laboratory work performed during April, May, and June 1976 on water-reactor-safety heat-transfer and flow problems. The following research and development areas are covered: (1) Loss of coolant Accident Research: Heat Transfer and Fluid Dynamics; (2) Transient Fuel Response and Fission-product Release Program; (3) Mechanical Properties of Zircaloy Containing Oxygen; and (4) Steam-explosion Studies.
Date: 1976?
Creator: Argonne National Laboratory
Partner: UNT Libraries Government Documents Department

Effects of Ternary Additions on Aluminum-35 w/o Uranium Alloys

Description: Abstract: "The effects of a number of ternary additions on the constitution, casting, and fabricating characteristics and the physical properties of aluminum-35 w/o uranium were investigated. Initial investigations were concerned with the effects of 3 w/o ternary additions on the microstructure and press-forging characteristics of the alloy. It was found that additions of this magnitude often introduced extrinsic phases in the alloy. At the 3 w/o level, additions of germanium, silicon, tin or zirconium inhibited the formation of UAl4 and thereby increased the content of the aluminum matrix in the alloy. It was also noted that these additions decreased the pressures required for extruding, and the tin addition also improved the homogeneity of cast shapes. Lead and palladium also improved the homogeneity of the cast material; however, neither of these was an effective inhibitor of UAl4 and free lead was detected in the alloy to which lead had been added at the ternary. From these studies it appears that tin and zirconium are as effective as silicon in enhancing the fabricating characteristics of aluminum-35 w/o uranium alloys, and may prove superior when evaluated on the bases of casting qualities and recycling characteristics."
Date: October 27, 1959
Creator: Daniel, Norman E.; Foster, Ellis L. & Dickerson, Ronald F.
Partner: UNT Libraries Government Documents Department

Hanford Works Analytical Manual for Reactor Process Water

Description: Purpose: "The Hanford Works Analytical Manual for Process Water is designed to specify the analytical methods to be applied for control purposes in the Reactor Section, Process Sub-Section laboratories. The procedures are in general form and serve as references rather than outlined laboratory instructions. The manual us designed to replace the "Hanford Works Manual," HW-12862."
Date: February 13, 1953
Creator: Hanford Works
Partner: UNT Libraries Government Documents Department

Light-Water-Reactor Safety Research Program

Description: Progress report on water-reactor-safety heat-transfer and flow problems. Covering the following research and development areas: loss-of-coolant accident research, transient fuel response and fission-product release program, mechanical properties of zircaloy containing oxygen, and steam-expulsion studies.
Date: December 1976
Creator: Argonne National Laboratory
Partner: UNT Libraries Government Documents Department

A Qualitative Assessment of Thorium-Based Fuels in Supercritical Pressure Water Cooled Reactors

Description: The requirements for the next generation of reactors include better economics and safety, waste minimization (particularly of the long-lived isotopes), and better proliferation resistance (both intrinsic and extrinsic). A supercritical pressure water cooled reactor has been chosen as one of the lead contenders as a Generation IV reactor due to the high thermal efficiency and compact/simplified plant design. In addition, interest in the use of thorium-based fuels for Generation IV reactors has increased based on the abundance of thorium, and the minimization of transuranics in a neutron flux; as plutonium (and thus the minor actinides) is not a by-product in the thorium chain. In order to better understand the possibility of the combination of these concepts to meet the Generation IV goals, the qualitative burnup potential and discharge isotopics of thorium and uranium fuel were studied using pin cell analyses in a supercritical pressure water cooled reactor environment. Each of these fertile materials were used in both nitride and metallic form, with light water reactor grade plutonium and minor actinides added. While the uranium-based fuels achieved burnups that were 1.3 to 2.7 times greater than their thorium-based counterparts, the thorium-based fuels destroyed 2 to 7 times more of the plutonium and minor actinides. The fission-to-capture ratio is much higher in this reactor as compared to PWR’s and BWR’s due to the harder neutron spectrum, thus allowing more efficient destruction of the transuranic elements. However, while the uranium-based fuels do achieve a net depletion of plutonium and minor actinides, the breeding of these isotopes limits this depletion; especially as compared to the thorium-based fuels.
Date: October 1, 2002
Creator: Weaver, Kevan Dean & Mac Donald, Philip Elsworth
Partner: UNT Libraries Government Documents Department

The Development and Testing of UO2 Fuel Systems for Water Reactor Applications: Summary Report, July 1, 1961 - June 15, 1962

Description: From introduction: "The work described in this report represents the Joint United States - European Atomic Energy Community effort which is in keeping with the spirit of cooperation in contributing to the common good by the sharing of scientific and technical information and minimizing the duplication of effort by the limited pool of technical talent available in Western Europe and the United States."
Date: June 1962
Creator: Murtha, B. E. & Chernock, W. P.
Partner: UNT Libraries Government Documents Department