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SYNBURN : a Fast-Reactor Fuel-Cycle Program

Description: The SYNBURN computer program for fast reactors will calculate all the neutronics necessary to completely characterize the equilibrium cycle as well as the startup to equilibrium cycles. The program's run time is very short and this makes the program suitable for survey of parametric studies. It can search on the cycle time for a specified burnup, for the shim control necessary for criticality as well as feed enrichments and the enrichment ratio among core zones. SYNBURN synthesizes in a very si… more
Date: 1976
Creator: Pizzica, P. A. & Meneley, D. A.
Partner: UNT Libraries Government Documents Department
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Analytical Investigation of Certain Aspects of LMFBR Subassembly-Failure Propagation

Description: An analytical investigation of certain problems in the area of subassembly-to-subassembly failure propagation in LMFBR's is described. Existing analyses of the response of the adjacent subassembly duct to mechanical loads are reviewed and summarized, and major uncertainties are identified. Additional analyses of the response of the adjacent subassembly to certain thermal loads are presented in two parts. In the first part, the effect of an external heat flux on duct melting and thermal stresses… more
Date: February 1976
Creator: Marr, William W.; Wang, P. Y.; Misra, B.; Padilla, A. & Crawford, R. M.
Partner: UNT Libraries Government Documents Department
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Avoiding Leakage Flow-Induced Vibration by a Tube-in-Tube Slip Joint

Description: Parameters and operating conditions (a stability map) were determined for which a specific slip-joint design did not cause self-excited lateral vibration of the two cantilevered, telescoping tubes forming the joint. The joint design featured a localized annular constriction. Flowrate, modal damping, tube engagement length, and eccentric positioning were among the parameters tested. Interestingly, all self-excited vibrations could be avoided by following a simple design rule: place constrictions… more
Date: October 1984
Creator: Mulcahy, T. M.
Partner: UNT Libraries Government Documents Department
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Unavailability Modeling and Analysis of Redundant Safety Systems

Description: Analytical expressions have been developed to estimate the average unavailability of an m-out-of-n (m/n, 1 less than or equal to m less than or equal to n less than or equal to 4) standby safety system of a nuclear power plant. The expressions take into account contributions made by testing, repair, equipment failure, human error, and different testing schemes. A computer code, ICARUS, has been written to incorporate these analytical equations. The code is capable of calculating the average una… more
Date: October 1979
Creator: Argonne National Laboratory. Reactor Analysis and Safety Division.
Partner: UNT Libraries Government Documents Department
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Proceedings of the NEANDC/NEACRP Specialists Meeting on Fast-Neutron Capture Cross Sections

Description: This proceedings contains the summaries and contents of a number of papers presented at the 1982 NEANDC/NEACRP specialists meeting on fast-neutron capture cross sections. The table of contents has been summarized to provide a sketch of the topical matter.
Date: April 1982
Creator: Smith, A. B. & Poenitz, W. P.
Partner: UNT Libraries Government Documents Department
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Leakage-Flow-Induced Vibration of a Tube-in-Tube Slip Joint

Description: The susceptibility of a cantilevered tube conveying water to self-excitation by leakage flow through a slip joint is assessed experimentally. The slip joint is formed by inserting a smaller, rigid tube into the free end of the cantilevered tube. Variations of the slip joint annular gaps and engagement lengths are tested, and several mechanisms for self-excitation are described.
Date: June 1983
Creator: Mulcahy, T. M.
Partner: UNT Libraries Government Documents Department
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Theory and Use of GIRAFFE for Analysis of Decay Characteristics of Delayed-Neutron Precursors in an LMFBR

Description: The application of the computer code GIRAFFE (General Isotope Release Analysis For Failed Elements) written in FORTRAN IV is described. GIRAFFE was designed to provide parameter estimates of the nonlinear discrete-measurement models that govern the transport and decay of delayed-neutron precursors in a liquid-metal fast breeder reactor (LMFBR). The code has been organized into a set of small, relatively independent and well-defined modules to facilitate modification and maintenance. The program… more
Date: July 1980
Creator: Gross, Kenny C.
Partner: UNT Libraries Government Documents Department
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Transient-Overpower Test E8 on FFTF-Type Low-Power-Irradiated Fuel

Description: Test E8 simulated a hypothetical $3/s transient overpower accident in an LMFBR using seven (plutonium, uranium) oxide fuel elements of the FTR type. The test elements were pre-irradiated in the PNL-10 assembly in EBR-II to 5 at.% burnup at 30 kW/m. The pre-irradiation in EBR-II caused a fuel-restructuring range characteristic of a low-to-moderate power microstructure for FTR. Failure predictions indicated that fuel with this microstructural characteristic would fail at a lower energy deposition… more
Date: 1977?
Creator: Simms, R.; Murphy, W. F.; Stanford, G. S. & Rothman, Alan B.
Partner: UNT Libraries Government Documents Department
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Cladding Failure by Local Plastic Instability

Description: Cladding failure is one of the major considerations in analysis of fuel-pin behavior during hypothetical accident transients since time, location, and nature of failure govern the early post-failure material motion and reactivity feedback. Out-of-pile thermal transient tests of both irradiated and unirradiated fast-reactor cladding show that local plastic instability, or bulging, often precedes rupture and that the extent of local instability limits the initial rip length. To investigate the de… more
Date: December 1977
Creator: Kramer, J. M. & Deitrich, L. W.
Partner: UNT Libraries Government Documents Department
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Failure of a High-Power Pin in a Simulated $3 /s Top Accident: Test E6 Final Report

Description: This report describes the Fuel Dynamics Test E6 and analyzes the test data. A cluster of six fresh FTR-type fuel pins surrounding a previously irradiated pin was tested to failure in a simulated $3/s FFTF accident.
Date: August 1978
Creator: Doerner, R. C.; Stahl, D.; Murphy, W. F. & Stanford, G. S.
Partner: UNT Libraries Government Documents Department
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IsotopesProduction Reactor: Summary of Complete Design

Description: Report describing an Isotope Production Reactor, which may be of interest to industrial groups studying the possibilities of entering the radioactive isotopes production field. Detailed drawings and specifications for the construction of the reactor are included.
Date: 1955
Creator: Winkleblack, R. K
Partner: UNT Libraries Government Documents Department
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Graphite Problems in Air-Cooled Reactors

Description: This report discusses problems affecting the long-term use of graphite in air-cooled reactors. The report identifies these problems as oxidation, radiation induced dimensional expansions and accumulation of stored energy. The report finds that "frequent low temperature annealing eliminates these problems and may extend the lifetime of the graphite indefinitely." (From abstract)
Date: 1962
Creator: Schweitzer, D. G.
Partner: UNT Libraries Government Documents Department
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Nuclear Reactor Project Progress Report, January 1948

Description: This report is a progress report detailing operations and ongoing projects at the Brookhaven National Laboratory. The report describes new developments with buildings and progress regarding ongoing experiments. The report includes photographs showing progress in the construction of the reactor and other images and figures that accompany the descriptions of projects.
Date: January 1, 1948
Creator: Borst, L. B. & Fox, Marvin
Partner: UNT Libraries Government Documents Department
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Report on the Brookhaven Nuclear Reactor Prepared for Reactor Safeguard Committee of the Atomic Energy Commission

Description: This technical report provides a general description of the Brookhaven National Laboratory, describing the nuclear characteristics of the Brookhaven reactor and more detailed descriptions of the features and instrumentation of the reactor.
Date: June 22, 1948
Creator: Brookhaven National Laboratory
Partner: UNT Libraries Government Documents Department
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Supplement to Report on the Brookhaven Nuclear Reactor Prepared for Reactor Safeguard Committee of the Atomic Energy Commission

Description: This technical report provides supplementary information on the Brookhaven nuclear reactor. It details added safety systems, tests, expounds on information included in the original report, describes liquid wastes system, and describes different procedures for operating the nuclear reactor.
Date: August 30, 1948
Creator: Brookhaven National Laboratory
Partner: UNT Libraries Government Documents Department
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The Escape of Fission Products From an Uranium Rod; Application to the B. N. L. Reactor

Description: Technical report covering the functions of the Oak Ridge reactor, difficulties encountered with cartridge failures in the Oak Ridge reactor, and possible solutions including the incorporation of leak detection systems into the design of the reactor.
Date: November 3, 1968
Creator: Chernick, J. & Kaplan, I.
Partner: UNT Libraries Government Documents Department
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Nuclear Reactor Progress Report

Description: Technical report describing the building of safety devices and features for the Oak Ridge reactor by the Reactor Safeguard Committee of the Atomic Energy Commission. Outlines the difficulties encountered in detailed design and construction operations for the facility.
Date: October 1, 1948
Creator: Brookhaven National Laboratory
Partner: UNT Libraries Government Documents Department
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Continuous Solvent Recovery Process Using Pulse Contacting Column

Description: From abstract: "This report presents the progress in the laboratory development of a continuous solvent recovery process for the tributyl phosphate-diluent mixture used in the Purex Process. Investigations were made with 1/2" diameter pulse columns, using a nine foot sodium carbonate contacting column and a four foot water wash column."
Date: April 1, 1952
Creator: Ellison, C. V. & Land, J. F.
Partner: UNT Libraries Government Documents Department
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Metallurgy Division Quarterly Progress Report for Period Ending October 31, 1950

Description: Technical report outlining the rate of production of modified MTR type fuel elements for the Bulk Shielding Facility has proceeded. Includes compatibility test that were started as a guide in the selection of materials suitable for fuel-element fabrication. [From Summary]
Date: February 8, 1951
Creator: Frye, J. H.; Miller, E. C. & Bridges, W. H.
Partner: UNT Libraries Government Documents Department
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Forced Convection Heat Transfer in Thermal Entrance Regions Part III. Heat Transfer to Liquid Metals

Description: Technical report covering the work done to explore heat transfer analytically and experimentally in liquid metals in turbulent flow within the thermal entrance region of circular tubes having uniform well temperature. Includes implications of this research. [From Summary]
Date: June 25, 1954
Creator: Harrison, William B.
Partner: UNT Libraries Government Documents Department
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