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captions transcript

[News Clip: Ageing Airplanes]

Description: Video footage from the KXAS-TV/NBC station in Fort Worth, Texas, to accompany a news story about the Ageing Aircraft Program.
Date: October 13, 1998
Duration: 1 minute 39 seconds
Creator: KXAS-TV (Television station : Fort Worth, Tex.)
Item Type: Refine your search to only Video
Partner: UNT Libraries Special Collections
captions transcript

[News Clip: Accident]

Description: Video footage from the WBAP-TV station in Fort Worth, Texas to accompany a news story about an accident on a Fort Worth highway after a hydraulic dump truck malfunctions, sending its bed flying upward and crashing into an overpass. The driver is injured, but not critically.
Date: June 11, 1956
Duration: 1 minute 02 seconds
Creator: WBAP-TV (Television station : Fort Worth, Tex.)
Item Type: Refine your search to only Video
Partner: UNT Libraries Special Collections
captions transcript

[News Clip: Parking lift]

Description: Video footage from the WBAP-TV station in Fort Worth, Texas to accompany a news story about a demonstration of an elevated parking lift device in Dallas designed to increase the capacity of parking lots.
Date: April 26, 1956
Duration: 58 seconds
Creator: WBAP-TV (Television station : Fort Worth, Tex.)
Item Type: Refine your search to only Video
Partner: UNT Libraries Special Collections
captions transcript

[News Clip: Thos. S. Byrne. Inc.]

Description: B-roll video footage from the WBAP-TV television station in Fort Worth, Texas, to accompany a news story about a construction site of Thos. S. Byrne. Inc..
Date: 1953-05-28/1954-06-02
Duration: 24 minutes 33 seconds
Creator: WBAP-TV (Television station : Fort Worth, Tex.)
Item Type: Refine your search to only Video
Partner: UNT Libraries Special Collections
open access

Utilization of Radioactive Isotopes in Coal Process Research

Description: "The experimental technique was checked out and the equipment put in working order for the study of the capacity and efficiency of the hydraulic cleaning of coal by water fluidization. The method to determine operating capacity consists of determining the segregation rate by dynamic tracing of radioactive mineral impurities of various size and density ranges, that are injected into the fluidized bed of coal. The equilibrium position of the injected tracer in the fluidized bed of solids is also … more
Date: unknown
Creator: Yavorsky, P. M. & Gorin, E.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

The Numerical Solution of a Parabolic System of Differential Equations Arising in Shallow Water Theory

Description: "A finite difference approximation to a non-linear set of parabolic differential equations arising in shallow water theory is given. These difference equations were used to determine the shape and rate of propagation of a hum of fluid down a channel of constant depth. The hump of fluid was found to spread instead of steepen, as is the case in the usual shallow water theory."
Date: October 15, 1960
Creator: Heller, Jack & Isaacson, Eugene
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Mixer-Settler Development: Operation Characteristics of a Large-Scale Mixer-Settler

Description: From abstract: "A pump-mix mixer-settler was demonstrated to have an overall efficiency greater than 90 per cent for the extraction of uranyl nitrate from tributyl phosphate at total flow rates up to 45 gallons per minute. Phase separation was satisfactory at 45 gallons per minute, at which flow rate the residence time in the settlers was 1-1/2 minutes. It appeared possible that a throughput approaching 60 gallons per minute would be operable although at an over-all efficiency of less than 90 p… more
Date: October 1956
Creator: Colven, Thomas J., Jr.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Characterization of jet breakup mechanisms observed from simulant experiments of molten fuel penetrating coolant

Description: The goal of this research program has been to add to our understanding of the breakup of molten fuel jets penetrating reactor coolant. Easily handled working fluids are used to simulate fuel jet breakup, so that detailed observations may be obtained from a relatively large number of experiments. The tools used for observing this behavior are high speed notion picture photography, Flash X-radiography, and X-ray cine. Jet breakup lengths are determined from motion pictures; the mechanisms by whic… more
Date: January 1, 1992
Creator: Jones, B. G.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Experiment data report for semiscale Mod-1 test S-06-6 (LOFT counterpart test). [PWR]

Description: Recorded test data are presented for Test S-06-6 of the Semiscale Mod-1 LOFT counterpart test series. These tests are among several Semiscale Mod-1 experiments conducted to investigate the thermal and hydraulic phenomena accompanying a hypothesized loss-of-coolant accident in a pressurized water reactor (PWR) system. Test S-06-6 was conducted from initial conditions of 15 792 kPa and 563 K to investigate the response of the Semiscale Mod-1 system to a depressurization and reflood transient foll… more
Date: September 1, 1977
Creator: Esparza, V. & Sackett, K. E.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Transmissivity iterative calculation routine: theory and numerical implementation

Description: A computer routine, the Transmissivity Iterative Routine (TIR), has been developed for calculating the hydraulic conductivity distribution in highly heterogeneous aquifers where characterization by field measurement methods alone would be prohibitive in cost. The routine yields the two-dimensional distribution of hydraulic conductivity averaged over the aquifer thickness. The agreement between the calculated and actual average conductivity is dependent on the degree to which the groundwater sys… more
Date: May 1, 1975
Creator: Cearlock, D. B.; Kipp, K. L. & Friedrichs, D. R.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Reactor safety research programs. Quarterly progress report, January 1--March 31, 1977

Description: The projects reported each quarter are the following: Gas Reactor Safety Evaluation, THOR Code Development, SSC Code Development, LMFBR and LWR Safety Experiments, Fast Reactor Safety Code Validation, Technical Coordination of Structural Integrity, and Fast Reactor Safety Reliability Assessment.
Date: May 1, 1977
Creator: Romano, A. J. (comp.)
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Multimegawatt space power reactors

Description: In response to the need of the Strategic Defense Initiative (SDI) and long range space exploration and extra-terrestrial basing by the National Air and Space Administration (NASA), concepts for nuclear power systems in the multi-megawatt levels are being designed and evaluated. The requirements for these power systems are being driven primarily by the need to minimize weight and maximize safety and reliability. This paper will discuss the present requirements for space based advanced power syst… more
Date: January 1, 1989
Creator: Dearien, J. A. & Whitbeck, J. F.
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
open access

Evaluation of the effects of break nozzle configuration in the Semiscale Mod-1 system. [PWR]

Description: The Semiscale Mod-1 Program has utilized two different break nozzle configurations in the test system. An evaluation has been made to determine the effect these break nozzle configurations have on system thermal-hydraulic response during a 200 percent double-ended cold leg break loss-of-coolant accident simulation. The first nozzle was a convergent-divergent nozzle (Henry nozzle) and the second, an elongated constant area throat nozzle. Analysis is confined primarily to system response phenomen… more
Date: August 1, 1977
Creator: Hanson, R. G.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

SIMMER-I, an LMFBR disrupted core analysis code

Description: SIMMER-I is a coupled neutronic, fluid dynamic computer program designed to analyze the dynamics of LMFBR disrupted cores. Either point kinetics or space dependent neutronics models can be used to calculate neutronic feedback effects. Multicomponent, two-phase flow models are used to predict the large scale material motion during core disruptive accidents. The effects of solid material on the fluid flow is included by simple models for core structure and frozen material. Mass, momentum, and ene… more
Date: January 1, 1976
Creator: Smith, L. L.; Boudreau, J. E.; Bell, C. R.; Bleiweis, P. B.; Barnes, J. F. & Travis, J. R.
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
open access

Analysis of the OECD-LOFT International Standard Problem 31 using SCDAP/RELAP5/MOD3

Description: The CORA-13 bundle heating and melting experiment performed at the Kernforechungszentrum, Karlaruhe, (KfK) was analyzed at the Idaho National Engineering Laboratory (INEL) using SCDAP/RELAP5/MOD3. This analysis was part of a systematic assessment of SCDAP/RELAP5/MOD3 for the US Nuclear Regulatory Commission to (a) evaluate the variances between calculated and observed behavior, (b) identify outstanding modeling deficiencies, and (c) to evaluate the impact of ongoing modeling improvements. A bri… more
Date: January 1, 1992
Creator: Hohorst, J. K. & Allison, C. M.
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
open access

Hydraulic pressure pulses with structural flexibility: test and analysis (LWBR Development Program)

Description: Pressure pulse tests were conducted with both solid and flexible test sections in a test vessel filled with room temperature water. Pressure pulses of magnitude up to 1150 psid and durations from 6 to 47 msec were generated with a drop hammer and piston pulse generator. FLASH-34 calculations show good agreement with the test data. In particular, FLASH-34 adequately predicts the decrease in peak pressure and the increase in pulse duration due to the presence of a flexible test section. Both test… more
Date: April 1976
Creator: Prelewicz, D. A.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Semiscale Mod-1 program and system description for the reflood heat transfer tests (test series 3)

Description: The purpose of the reflood heat transfer test series is to investigate the reflood heat transfer characteristics of the Semiscale Mod-1 electrically heated core which contains rods with 5.5-ft heated lengths. The data provided by these tests are expected to be valuable in the calculation of core and system response during the reflood portion of integral-type tests to be performed later in the Mod-1 program. Presented are descriptions and objectives of the overall Semiscale Mod-1 program and of … more
Date: May 1, 1976
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Development of solutions to benchmark piping problems. [EPIPE code]

Description: Piping analysis is one of the most extensive engineering efforts required for the design of nuclear reactors. Such analysis is normally carried out by use of computer programs which can handle complex piping geometries and various loading conditions, (static or dynamic). A brief outline is presented of the theoretical background for the EPIPE program, together with four benchmark problems: two for the static case and two for the dynamic case. The results obtained from EPIPE runs compare well wi… more
Date: January 1, 1976
Creator: Reich, M.; Chang, T. Y. & Prachuktam, S.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Effects of duct configuration on flow and temperature structure in sodium-cooled 19-rod simulated LMFBR fuel bundles with helical wire-wrap spacers

Description: Thermal-hydrodynamic testing of sodium-cooled 19-rod simulated LMFBR fuel bundles is being conducted at the O ak Ridge National Laboratory in the Fuel Failure Mockup (FFM), an engineering-scale high-temperature sodium facility which provides prototypic flows, temperatures and power densities. Electrically heated bundles have been tested with two scalloped and two hexagonal duct configurations. Peripheral helical flows, attributed to the spacers, have been observed with strengths dependent upon … more
Date: January 1, 1976
Creator: Wantland, J. L.; Fontana, M. H.; Gnadt, P. A.; Hanus, N.; MacPherson, R. E. & Smith, C. M.
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
open access

Numerical model for two-dimensional hydrodynamics and energy transport. [VECTRA code]

Description: The theoretical basis and computational procedure of the VECTRA computer program are presented. VECTRA (Vorticity-Energy Code for TRansport Analysis) is designed for applying numerical simulation to a broad range of intake/discharge flows in conjunction with power plant hydrological evaluation. The code computational procedure is based on finite-difference approximation of the vorticity-stream function partial differential equations which govern steady flow momentum transport of two-dimensional… more
Date: June 1, 1973
Creator: Trent, D. S.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Flow-induced vibration of component cooling water heat exchangers

Description: This paper presents an evaluation of flow-induced vibration problems of component cooling water heat exchangers in one of Taipower's nuclear power stations. Specifically, it describes flow-induced vibration phenomena, tests to identify the excitation mechanisms, measurement of response characteristics, analyses to predict tube response and wear, various design alterations, and modifications of the original design. Several unique features associated with the heat exchangers are demonstrated, inc… more
Date: January 1, 1990
Creator: Yeh, Y. S.; Chen, S. S. (Taiwan Power Co., Taipei (Taiwan). Nuclear Engineering Dept. & Argonne National Lab., IL (USA))
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
open access

Gas-Cooled Reactor Programs annual progress report for period ending December 31, 1973. [HTGR fuel reprocessing, fuel fabrication, fuel irradiation, core materials, and fission product distribution; GCFR fuel irradiation and steam generator modeling]

Description: Progress is summarized in studies relating to HTGR fuel reprocessing, refabrication, and recycle; HTGR fuel materials development and performance testing; HTGR PCRV development; HTGR materials investigations; HTGR fuel chemistry; HTGR safety studies; and GCFR irradiation experiments and steam generator modeling.
Date: April 1, 1976
Creator: Kasten, P. R.; Coobs, J. H. & Lotts, A. L.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Analysis of BWR pressure suppression pool dynamics

Description: The design basis loss of coolant accident (LOCA) for light water nuclear reactors postulates a major break in a coolant line. Both the response of the reactor vessel and its mechanical system as well as the response of the pressure suppression containment system exterior to the pressure vessel are of primary interest following such an event. The ability to determine system response and the suitability of particular mechanical and structural design features in both cases is predicted on the comp… more
Date: August 30, 1976
Creator: McCauley, E. W.; Martin, R. W. & Sutton, S. B.
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
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