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Thermal-neutron capture for A=36-44

Description: The prompt gamma-ray data of thermal- neutron captures fornuclear mass number A=26-35 had been evaluated and published in "ATOMICDATA AND NUCLEAR DATA TABLES, 26, 511 (1981)". Since that time the manyexperimental data of the thermal-neutron captures have been measured andpublished. The update of the evaluated prompt gamma-ray data is verynecessary for use in PGAA of high-resolution analytical prompt gamma-rayspectroscopy. Besides, the evaluation is also very needed in theEvaluated Nuclear Structure Data File, ENSDF, because there are no promptgamma-ray data in ENSDF. The levels, prompt gamma-rays and decay schemesof thermal-neutron captures fornuclides (26Mg, 27Al, 28Si, 29Si, 30Si,31P, 32S, 33S, 34S, and 35Cl) with nuclear mass number A=26-35 have beenevaluated on the basis of all experimental data. The normalizationfactors, from which absolute prompt gamma-ray intensity can be obtained,and necessary comments are given in the text. The ENSDF format has beenadopted in this evaluation. The physical check (intensity balance andenergy balance) of evaluated thermal-neutron capture data has been done.The evaluated data have been put into Evaluated Nuclear Structure DataFile, ENSDF. This evaluation may be considered as an update of the promptgamma-ray from thermal-neutron capture data tables as published in"ATOMIC DATA AND NUCLEAR DATA TABLES, 26, 511 (1981)".
Date: January 1, 2003
Creator: Chunmei, Z. & Firestone, R.B.
Partner: UNT Libraries Government Documents Department

Full-scale wind-tunnel and flight tests of a Fairchild 22 airplane equipped with external-airfoil flaps

Description: Wind-tunnel and flight tests have been made of a Fairchild 22 airplane equipped with a wing having external-airfoil flaps that also perform the function of ailerons. Lift, drag, and pitching-moment coefficients of the airplane with several flap settings, and the rolling- and yawing-moment coefficients with the flaps deflected as ailerons were measured in the full-scale tunnel with the horizontal tail surfaces and propeller removed. The effect of the flaps on the low speed and on the take-off and landing characteristics, the effectiveness of flaps when used as ailerons, and the forces required to operate them as ailerons were determined in flight. The wind-tunnel tests showed that the flaps increased the maximum lift coefficient of the airplane from 1.51 with the flap in the minimum drag position to 2.12 with the flap in the minimum drag position to 2.12 with the flap deflected 30 degrees. In the flight tests the minimum speed decreased from 46.8 miles per hour with the flaps up to 41.3 miles per hour with the flaps deflected. The required take-off run to attain a height of 50 feet was reduced from 820 to 750 feet and the landing run from a height of 50 feet was reduced from 930 to 480 feet. The flaps for this installation gave lateral control that was not entirely satisfactory. Their rolling action was good but the adverse yaw resulting from their use was greater than is considerable, and the stick forces required to operate them increased too rapidly with speed.
Date: July 1937
Creator: Reed, Warren D. & Clay, William C.
Partner: UNT Libraries Government Documents Department

Comparative Flight and Full-Scale Wind-Tunnel Measurements of the Maximum Lift of an Airplane

Description: "Determinations of the power-off maximum lift of a Fairchild 22 airplane were made in the NACA full-scale wind tunnel and in flight. The results from the two types of test were in satisfactory agreement. It was found that, when the airplane was rotated positively in pitch through the angle of stall at rates of the order of 0.1 degree per second, the maximum lift coefficient was considerably higher than that obtained in the standard tests, in which the forces are measured with the angles of attack fixed. Scale effect on the maximum lift coefficient was also investigated" (p. 161).
Date: October 26, 1937
Creator: Silverstein, Abe; Katzoff, S. & Hootman, James A.
Partner: UNT Libraries Government Documents Department

REACTOR PHYSICS QUARTERLY REPORT JANUARY, FEBRUARY, MARCH 1970

Description: The objective of the Reactor Physics Quarterly Report is to inform the scientific community in a timely manner of the technical progress made on the many phases of reactor physics work within the laboratory. The report contains brief technical discussions of accomplishments in all areas where significant progress has been made during the quarter.
Date: May 1, 1970
Creator: Schmid, L. C.; Clayton, E. D. & Heineman, R. E.
Partner: UNT Libraries Government Documents Department

STATISTICAL ANALYSIS AND MODELING OF GAP CONDUCTANCE DATA FOR REACTOR FUEL RODS CONTAINING UO2 PELLETS

Description: The purpose of this study was threefold: To examine a large body of in-reactor data for UO{sub 2} pellet fuel where internal temperatures have been measured, and to estimate fuel surface temperature, cladding inner temperature, and thus gap conductance under a consistent set of assumptions. To estimate the variance (due to experimental uncertainties) in the inferred gap conductance values. To attempt a correlation of the gap conductance values with design parameters and operating conditions (e.g., with cold diametral gap and local linear power).
Date: May 1, 1974
Creator: Lanning, D. D.; Hann, C. R. & Gilbert, E. S.
Partner: UNT Libraries Government Documents Department

PAR Loop Schedule Review

Description: The schedule for the installation of the PAR slurry loop experiment in the ·South Facility af the ORR has been reviewed and revised. Changed design philosophy to include maintainability of the loop auxiliaries required extension of the main construction period to the end of,June, with a three month period ending in September, for test and run in during which construction will be completed.
Date: February 28, 1958
Creator: Schaffer, Jr. & W.F.
Partner: UNT Libraries Government Documents Department

PAR Loop Schedule Review

Description: The schedule for the installation of the PAR slurry loop experiment in the South Facility of the ORR has been reviewed and revised. The design, fabrication, and installation is approximately two weeks behind schedule at this time due to many factors; however, indications are that this time can be made up. Design is estimated to be 56 per cent complete, fabrication 27 per cent complete-and installation 11 per cent complete:
Date: March 31, 0958
Creator: Schaffer, Jr. & W.F.
Partner: UNT Libraries Government Documents Department

PAR Loop Schedule Review

Description: The status of the overall design, fabrication, and installation of the component items of the PAR loop experiment in the ORR is reviewed.
Date: January 15, 1958
Creator: Schaffer, Jr. & W.F.
Partner: UNT Libraries Government Documents Department

PAR Loop Schedule Review

Description: The schedule for the installation of the PAR slurry loop experiment in the South Facility of the ORR has been reviewed and revised. The design, fabrications and Installation is approximately two weeks behind schedule at this time due to many factors; however, indications are that this time can be made up. Design is estimated to be 75% complete, fabrication 32% complete and installation 12% complete.
Date: April 30, 1958
Creator: Schaffer, Jr. & W.F.
Partner: UNT Libraries Government Documents Department

PAR Loop Schedule Review

Description: The status of the overall schedule for design, fabrication, and installation of the component items of the PAR loop experiment in the ORR has been brought up to date and reviewed. This is the first review since the original issue of the schedule
Date: October 16, 1957
Creator: Schaffer, Jr. & W.F.
Partner: UNT Libraries Government Documents Department

PARAMETRIC REACTIVITY TRANSIENT ANALYSES FOR THE FFTF NUCLEAR PROOF TEST REACTOR

Description: Fault tree techniques have been used to identify possible failure paths within the NPTR which could lead to core disassembly. The analysis o f the various faults has led to formulation of design requirements, protective system requirements, and administrative restraints required to prevent accidents from these faults. Transient analyses were performed using the heat transfer-nuclear kinetics codes, Nutiger-II, FORE-II, and MELT-II . To verify results, intercomparison studies were made between the codes. The codes were i n good general agreement. Each code was found to exhibit different advantages and disadvantage. Inherent reactivity feedback effects were assessed in the analysis. With the assumed core parameters, there appears to be sufficient Doppler to prolong a nuclear transient to allow protective action to prevent fuel from melting. The use of average values of the feedback coefficients smeared over the entire core does not appear to be an acceptable method with spacially dependent temperatures. In the thermal analysis, the fuel pin gap coefficient and sodium film coefficient do not appear to be highly sensitive parameters for transient analysis. Power transients resulting from reactivity insertions of from 2$/sec to 20$/sec have been examined in detail. Sodium will be molten before fuel melting occurs for accidents within this range. For the smaller ramp rates (< 4$/sec), sodium nay even reach vaporization temperatures before any fuel melts. Power transients terminated by effective protective action were investigated. It i s believed p o s s i b l e t o design a scram system, with the . present state of the art, to prevent sodium from melting for a reactivity ramp up to at least 6$/sec. This same system would prevent fuel melting for a reactivity ramp up to 15$/sec. Sodium thermal expansion will play a very important role in a core disassembly. When the average sodium ...
Date: January 1, 1970
Creator: Schade, A. R.
Partner: UNT Libraries Government Documents Department

POSTIRRADIATION EXAMINATION OF CENTRIFUGALLY BONDED EBR-11 DRIVER FUEL

Description: BNW was requested by AEC/DRDT to assist ANL with the postirradiation examination of EBR-II driver fuel (U + 5Fs) pins that became shortened during irradiation. To date, three irradiated pins and one nonirradiated pin were examined.
Date: July 31, 1969
Creator: Leggett, R. D.; Hann, D. R.; Last, G. A. & Gruber, W. J.
Partner: UNT Libraries Government Documents Department

FAST FLUX TEST FACILITY CONCEPTUAL COMPONENT DESIGN DISCRIPTION FOR THE REACTOR NUCLEAR CONTROL COMPONENTS No. 33

Description: This document describes the nuclear control component of the Fast Test Reactor (FTR) . The Fast Test Reactor is t he central test bed of the Fast Flux Test Facility (FFTF). The Reactor Nuclear Control Components described in this document consist of neutron absorbing elements which are moved axially into and out of the general area of the active portion of the core. The electromechanical drive housings are mounted on the reactor cover and are part of the pressure boundary of the vessel and cover during reactor operation. Drive lines (extension shafts) extend through the cover and are connected to the poison element. The element is guided in the core throughout its travel by a flow duct which resides in the c or e grid plate receptacle. Sodium coolant from the primary loop is used to cool the neutron absorbing rods. This Conceptual Component Design Description (CCDD) suppor t s and expands the requirements of the Overall Conceptual Systems Design Description . Specifically , it establishes the reactor nuclear control design requirements; describes the current reference design of this control; defines safety, operational · and maintenance principles; indicates unresolved problems ; and identifies the principal interfaces affecting the reactor control component functional requirements and design configuration. Included are functions and design requirements, a physical description of the system, safety considerations, principles of operation, and maintenance principles.
Date: October 1, 1969
Partner: UNT Libraries Government Documents Department

FAST FLUX TEST FACILITY CONCEPTUAL FACILTY DESIGN DESCRIPTION FOR THE INERT GAS CELL EXAMINATION FACILITY NO. 71

Description: The purpose of this Conceptual Facility Design Description (CFDD) is to provide a technical description of the Inert Gas Cell Examination Facility such that agreement with RDT on a Conceptual Design can be reached . The CFDD also serves to establish a common understanding of the facility concept among all responsible FFTF Project parties including the Architect Engineer and Reactor Designer. Included are functions and design requirements, a physical description of the facility, safety considerations, principles of operation, and maintenance principles.
Date: December 12, 1968
Partner: UNT Libraries Government Documents Department

FAST FLUX TEST FACILITY CONCEPTUAL SYSTEM DESIGN DESCRIPTION FOR THE BUILDING ELECTRICAL POWER SYSTEM No. 12

Description: The Building Electrical Power System, transmits, distributes and controls the electrical power utilized by the equipment of all of the FFTF system. Included are system functions and design requirements, the physical description of the system, safety considerations, principles of operations, and maintenance principles.
Date: July 3, 1968
Partner: UNT Libraries Government Documents Department

FAST FLUX TEST FACILITY CONCEPTUAL SYSTEM DESIGN DESCRIPTION FOR THE HEATING AND VENTILATION SYSTEM NO. 25

Description: The Heating and Ventilation System provides the atmospheric conditions in FFTF as required to assure that plant objectives can be met in a safe and practical manner. Included are functions and design requirements, a physical description of the system, safety considerations, principles of operation, and maintenance principles.
Date: December 5, 1969
Partner: UNT Libraries Government Documents Department

FAST FLUX TEST FACILITY CONCEPTUAL SYSTEM DESIGN DESCRIPTION FOR THE PLANT FIRE PROTECTION SYSTEM No. 26

Description: The fire protection system for the FFTF is required for the safety of personnel and the protection of property. Included are functions and design requirements, a detailed description of the system, safety considerations, principles of operation, and maintenance principles.
Date: August 20, 1968
Partner: UNT Libraries Government Documents Department