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66,732 Matching Results

Start Over Access Open Access Day 31st

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Best Match Title Creator Date Created (Newest) Date Created (Oldest) Date Added (Newest) Date Added (Oldest)
EXPERIMENTAL INVESTIGATION OF THE EFFECTS OF ULTRASONIC VIBRATIONS ON BURNOUT HEAT FLUX WITH BOILING WATER. Quarterly Technical Progress Report, October-December 1960 (open access)

EXPERIMENTAL INVESTIGATION OF THE EFFECTS OF ULTRASONIC VIBRATIONS ON BURNOUT HEAT FLUX WITH BOILING WATER. Quarterly Technical Progress Report, October-December 1960

>The effects of an ultrasonic field on the maximum nucleate heat flux that can be sustained by boiling water in a flow system are being investigated. Design and procurement of apparatus is underway. (M.C.G.)
Date: October 31, 1962
Creator: Romie, F.E.
Object Type: Report
System: The UNT Digital Library
AN INTEGRATED CIRCUIT CONTROL SYSTEM FOR THE PEWEE REACTOR. (open access)

AN INTEGRATED CIRCUIT CONTROL SYSTEM FOR THE PEWEE REACTOR.

None
Date: October 31, 1969
Creator: Strait, B.G. & Lang, R.M.
Object Type: Report
System: The UNT Digital Library
DELAYED LUMINESCENCE IN ALKALI HALIDES UNDER F BLEACHING. (open access)

DELAYED LUMINESCENCE IN ALKALI HALIDES UNDER F BLEACHING.

None
Date: October 31, 1969
Creator: Manilerd, C & Kim, Y W
Object Type: Report
System: The UNT Digital Library
Evaluate fundamental approaches to longwall dust control. Phase III report (open access)

Evaluate fundamental approaches to longwall dust control. Phase III report

The overall objective of the contract is to evaluate the effectiveness of available dust control technology for double-drum shearer longwall sections in a coordinated, systematic program at a few longwall test sections and to make the results available to the entire coal mining industry. This program is investigating nine different dust control techniques. These nine subprograms encompass a broad range of dust control measures ranging from administrative controls to new hardware. They span not only presently employed methods but also those recently adopted in the United States and those proposed for the future. This report documents the Phase III effort on each of the subprograms. For clarity, the report is divided in sections by subprogram as follows: Section 2, Subprogram A - passive barriers/spray air movers for dust control; Section 3, Subprogram B - practical aspects of deep cutting; Section 4, Subprogram C - stage loader dust control; Section 5, Subprogram D - longwall automation technology; Section 6, Subprogram E - longwall application of ventilation curtains; Section 7, Subprogram F - reversed drum rotation; Section 8, Subprogram G - reduction of shield generated dust; Section 9, Subprogram H - air canopies for longwalls; and Section 10, Subprogram I - mining …
Date: March 31, 1984
Creator: Babbitt, C.; Bartlett, P.; Kelly, J.; Ludlow, J.; Mangolds, A.; Rajan, S. et al.
Object Type: Report
System: The UNT Digital Library
COMPUTER SIMULATION OF HOT-ZONE REACTIONS. II. (open access)

COMPUTER SIMULATION OF HOT-ZONE REACTIONS. II.

None
Date: October 31, 1969
Creator: Anselmo, V.C. & Rekart, L.
Object Type: Report
System: The UNT Digital Library
IDAHO DIVISION SUMMARY REPORT, APRIL THROUGH SEPTEMBER 1961 (open access)

IDAHO DIVISION SUMMARY REPORT, APRIL THROUGH SEPTEMBER 1961

Research and development progress is reported on TREAT, BORAX V, ZPR- III, EBR-II, and the reactor operations personnel training program. (M.C.G.)
Date: October 31, 1962
Creator: unknown
Object Type: Report
System: The UNT Digital Library
Quarterly Status Report on the Advanced Plutonium Fuels Program, October 1-- December 31, 1967 (open access)

Quarterly Status Report on the Advanced Plutonium Fuels Program, October 1-- December 31, 1967

None
Date: December 31, 1968
Creator: unknown
Object Type: Report
System: The UNT Digital Library
RADIOISOTOPE FUELED AUXILIARY POWER UNIT. Quarterly Progress Report No. 1, January 2-April 2, 1957 (open access)

RADIOISOTOPE FUELED AUXILIARY POWER UNIT. Quarterly Progress Report No. 1, January 2-April 2, 1957

Progress on an isotope-fueled auxiliary power unit is reported. Based on the power requirements of 260 W, it was concluded that Ce/sup 144/ should be used as fuel. Estimates were made of fuel availability and unit cost and weight at power levels of 133, 300, 500, and 1000 W(e). Fuel development, boiler development, system and operational considerations, and the power conservation system are discussed. (M.C.G.)
Date: October 31, 1962
Creator: Silverstein, C.C. & Behmer, R.E. comps.
Object Type: Report
System: The UNT Digital Library
EXPERIMENTAL APPARATUS AND TECHNIQUES FOR HIGH TEMPERATURE COMPATIBILITY STUDIES (open access)

EXPERIMENTAL APPARATUS AND TECHNIQUES FOR HIGH TEMPERATURE COMPATIBILITY STUDIES

The development of apparatus and laboratory techniques for the study of materials compatibility with 1500 to 2200 deg F potassium was attempted. Techniques for corrosion tab preparation, dry box capsule filling and sampling, and vacuum filling and sampling are described. Apparatus for rotating capsule testing to 2000 F, rotating capsule testing to 2400 deg F, and anisothermal see-saw'' capsule testing is also described. (auth)
Date: May 31, 1961
Creator: Smith, W.T.
Object Type: Report
System: The UNT Digital Library
Proceedings of the conference on research for the development of geothermal energy resources held in Pasadena, California, September 23--25, 1974 (open access)

Proceedings of the conference on research for the development of geothermal energy resources held in Pasadena, California, September 23--25, 1974

None
Date: December 31, 1974
Creator: unknown
Object Type: Article
System: The UNT Digital Library
SEFOR FOLLOW-ON PROGRAM PHASE A. Final Report, June 15, 1971--December 31, 1971 (open access)

SEFOR FOLLOW-ON PROGRAM PHASE A. Final Report, June 15, 1971--December 31, 1971

None
Date: December 31, 1972
Creator: Arterburn, J. O.
Object Type: Report
System: The UNT Digital Library
Compilation of Current Technical Experience at Enrico Fermi Atomic Power Plant, November 1968. (open access)

Compilation of Current Technical Experience at Enrico Fermi Atomic Power Plant, November 1968.

The scope of this report includes all phases of current operations and maintenance experience concerning the nuclear portion and related systems of the Enrico Fermi Power Plant.
Date: October 31, 1969
Creator: Costello, R. H.
Object Type: Report
System: The UNT Digital Library
Animal Metabolic Studies of Strontium and Calcium With Specific Reference to Fallout Radionuclides. Progress Report No. 5, August 16, 1967-August 15, 1968. (open access)

Animal Metabolic Studies of Strontium and Calcium With Specific Reference to Fallout Radionuclides. Progress Report No. 5, August 16, 1967-August 15, 1968.

This report provides a summary of animal metabolic studies of strontium and calcium with specific reference to fallout radionuclides.
Date: October 31, 1969
Creator: unknown
Object Type: Report
System: The UNT Digital Library
REACTOR DEVELOPMENT PROGRAM PROGRESS REPORT, JANUARY 1967 (open access)

REACTOR DEVELOPMENT PROGRAM PROGRESS REPORT, JANUARY 1967

None
Date: December 31, 1967
Creator: unknown
Object Type: Report
System: The UNT Digital Library
Pathfinder Atomic Power Plant Analog Simulator. (open access)

Pathfinder Atomic Power Plant Analog Simulator.

The steady-state and dynamlc characterlstics of the Pathfinder systems were simulated on a dual-console Pace Analog Computer. The derivation of the system equations, the assumptions involved, their numerical evaluation, and their conversion to analog circuitry are described. The Pathfinder system is unique because of the internal nuclear superheater, and controlled, forced recirculation. In simulating this system the following major assumptions were maden the reactor is a boiling-water type; moderated and cooled with saturated, light water; pressurized between 400 and 800 psiai and has a neutron flux distribution that is spatially invariant. All the importanit non-linearities are retained, thus permitting accurate solutions of large system disturbances. The neutron kinetics equations, with their six groups of delayed neutrons, are simulated with power feedbacks through reactor pressure, steam flow, core inlet subcooling, and fuel- element temperature. Particular attention ls devoted to the accurate simulation of fuel-element heat transfer; the reactor pressure-control system, which operates the turbine inlet valves; and the effect of core inlet subcooling, sinee these were found to have pronounced effects on reactor performance. The transient temperatures at the superheater hot spot and exit are generated. Enough flexibility ss included, so that all important disturbanees possible in the actual plant can …
Date: January 31, 1962
Creator: Crimmins, D. H.; Mohr, D. & Stone, J. T.
Object Type: Report
System: The UNT Digital Library
Test and Evaluation of Alco/BLH Prototype Sodium-Heated Steam Generator: Final Report (open access)

Test and Evaluation of Alco/BLH Prototype Sodium-Heated Steam Generator: Final Report

A 30-Mwt prototype sodium-to-sodium intermediate heat exchanger and a 30-Mwt prototype sodium-heated steam generator were tested in combined operation in its Sodium Components Test Installation. This report contains the results of test and evaluation of the steam generator. During plant performance tests, performance degradation was observed, which resulted in the initiation of a diagnostic test series. This test series revealed that under certain operating conditions, the thermohydraulic characteristic of the steam generator changed either suddenly or gradually, resulting in overall performance degradation. A structural failure, requiring retirement of the unit, occurred before the diagnostic test series and analytical support effort were completed. This report describes the thermohydraulic and structural performance, including the structural failures, and related evaluation analyses of the Alco/BLH prototype steam generator performed prior to termination of the test and evaluation program. In addition, the report presents a post-test examination plan to obtain data that could possibly explain the cause of performance anomalies and structural failures experienced during testing.
Date: January 31, 1971
Creator: Kaplan, C. J.; Auge, L. J.; Cho, S. M.; Hanna, R. W.; Prevost, J. R.; Steger, N. A. et al.
Object Type: Report
System: The UNT Digital Library
THRESHOLD DISPLACEMENT ENERGY MEASUREMENTS ON Ta AND Nb. (open access)

THRESHOLD DISPLACEMENT ENERGY MEASUREMENTS ON Ta AND Nb.

None
Date: October 31, 1969
Creator: Youngblood, G.; Myhra, S. & DeFord, J.W.
Object Type: Report
System: The UNT Digital Library
Direct Energy Conversion Studies With Emphasis on Those Involving Nuclear Radiation. (open access)

Direct Energy Conversion Studies With Emphasis on Those Involving Nuclear Radiation.

None
Date: October 31, 1969
Creator: Miley, G. H.
Object Type: Report
System: The UNT Digital Library
Validation of the kinetic model for predicting the composition of chlorinated water discharged from power plant cooling systems (open access)

Validation of the kinetic model for predicting the composition of chlorinated water discharged from power plant cooling systems

The purpose of this report is to present a validation of a previously described kinetic model which was developed to predict the composition of chlorinated fresh water discharged from power plant cooling systems. The model was programmed in two versions: as a stand-alone program and as a part of a unified transport model developed from consistent mathematical models to simulate the dispersion of heated water and radioisotopic and chemical effluents from power plant discharges. The results of testing the model using analytical data taken during operation of the once-through cooling system of the Quad Cities Nuclear Station are described. Calculations are also presented on the Three Mile Island Nuclear Station which uses cooling towers.
Date: October 31, 1977
Creator: Lietzke, M. H.
Object Type: Report
System: The UNT Digital Library
Halogen Atom Reactions Activated by Radiative Neutron Capture and /sup 82m/ Br and /sup 130m/I Isomeric Transition. Progress Report No. 4, February 1969-- February 1970 (open access)

Halogen Atom Reactions Activated by Radiative Neutron Capture and /sup 82m/ Br and /sup 130m/I Isomeric Transition. Progress Report No. 4, February 1969-- February 1970

None
Date: December 31, 1970
Creator: unknown
Object Type: Report
System: The UNT Digital Library
Investigation of mechanically hard, chemically inert antireflection coatings for photovoltaic solar modules. Final technical report, April 1, 1980-March 31, 1981 (open access)

Investigation of mechanically hard, chemically inert antireflection coatings for photovoltaic solar modules. Final technical report, April 1, 1980-March 31, 1981

The overall objective of this program is to determine the optical properties of i-Carbon (diamond-like) films and determine if these films can be developed into antireflecting (AR) coatings for silicon solar cells. The i-C films have been produced on glass, silicon, and KCl by radio frequency (RF) plasma decomposition of the alkane gases. Films were also produced on silicon solar cells by low-energy ion beam techniques. These coatings did not perform as well as those made from hydrocarbon gases. Significant progress has been made in understanding the deposition parameters that affect the optical properties of the films. The optical constants n and k have been determined over a large range of process parameters and source gas. The degree of hydrogen incorporation in these films has been studied by SIMS analysis. It was found that the lower optically absorbing films contain more hydrogen. This hydrogen does not, however, manifest itself in fundamental C-H absorption bands in the infrared. Very efficient single-layer quarter-wave i-C AR coatings have been produced on single-crystal and SOC Si solar cells. An increase in cell efficiency of 40% over uncoated cells has been achieved.
Date: March 31, 1981
Creator: Moravec, T.J.
Object Type: Report
System: The UNT Digital Library
METALLURGY DIVISION ANNUAL REPORT FOR 1961 (open access)

METALLURGY DIVISION ANNUAL REPORT FOR 1961

8 < 8 7 8 7 < 5 8 6 ; : 9: 2 8 9 9 ; ; < 9 : 9 : 8 8 I of transformation and fusion, of U and U- fissium alloys were completed during the year. Data are also included on cladding penetration by molten U-fissium alloys and molten Pu fuel. Irradiation studies of U-fissium and Ufissium-Zr alloys were conducted. Progress is reported on the development of methods and equipment for remote refabrication of EBR-II fuel. Development and Fabrication of EBR-I Core IV Fuel Elements. A program to investigate methods of fabricating Pu-Al reference alloy for EBR-I Core IV is described along with the production of fuel rods for this core. The procurement, fabrication, and inspection of components other than Ra material for Core N of EBR-I was continued. Data obtained in nondestructive inspection of EBR-I Core IV components are presented along with data concerning properties of and radiation effects on Al-Pu alloys. EBWR Fabrication Programs. The work in these programs was largely concenned with fabrication of a control-rod-drive assembly made of 17- 4 PH stainless steel. Fabrication of Borax-V Boiling and Superheater Fuel Elements, Control Rod Drive Shafts, and Control Rods. Data are …
Date: October 31, 1962
Creator: unknown
Object Type: Report
System: The UNT Digital Library
Fast Reactor Systems for Space Power. (open access)

Fast Reactor Systems for Space Power.

None
Date: October 31, 1969
Creator: Johnson, C. E.
Object Type: Report
System: The UNT Digital Library
THERMAL DIFFUSIVITY OF SX-5 GRAPHITE FROM 800$sup 0$ TO 2800$sup 0$C. (open access)

THERMAL DIFFUSIVITY OF SX-5 GRAPHITE FROM 800$sup 0$ TO 2800$sup 0$C.

None
Date: October 31, 1969
Creator: Morrison, B.H.
Object Type: Report
System: The UNT Digital Library