49 Matching Results

Search Results

Results: 1 - 24 next
open access

SNAP 19 Phase 3 Final Report: Volume 1, Power Supply System

Description: Report providing an account of phase 3 of the SNAP 19 radioisotope thermometric generator program, under which prototype-qualified and acceptance tested flight power supplies for the Nimbus B spacecraft were produced. This volume covers the complete power supply system, including a description of the power supply, interface with Nimbus B spacecraft, testing, power supply reliability, aerospace nuclear safety, aerospace ground equipment, and spacecraft integration.
Date: May 1968
Creator: Martin Marietta Corporation
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Safety Evaluation of PNPF Modifications

Description: "The purpose of this report is to examine the safety aspects of PNPF restart on continued operation, after completion of the core cleanup and system modifications."
Date: May 1, 1969
Creator: Huntsinger, M. & Hart, R. S.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Quarterly Technical Progress Report, AEC Unclassified Programs: Fiscal Year 1968

Description: Quarterly report with the objectives of evaluating, producing, and maintaining of an up-to-dat set of basic nuclear data; producing and evaluating of multigroup constants; and the improvement of present day methods of neutronic calculations as relates to microscopic and macroscopic nuclear data, for unclassified research sponsored by the U.S. Atomic Energy Commission during FY 1968.
Date: May 24, 1969
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Annual Technical Progress Report, AEC Unclassified Programs: Fiscal Year 1968

Description: Annual report with the objectives of evaluating, producing, and maintaining an up-to-date set of basic nuclear data; producing and evaluating multigroup constants; and improving of present day methods of neutronic calculations as related to microscopic and macroscopic nuclear data, for unclassified research sponsored by the U.S. Atomic Energy Commission during FY 1968.
Date: May 24, 1969
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Development of Pulsed Neutron Application to Power Reactor Start-Up Procedures. Fourth Quarterly Progress Report, January 1-March 31, 1963

Description: Activities in a program to develop techniques in the use of pulsed neutron sources to measure shutdown parameters related to large thermal power reactors are reported. The experimental work centers around aspects of detecting neutrons in the presence of 10/sup 7/ r/hr gamma fields. Boric acid experiments and Humboldt Bay experiments are reported.
Date: May 13, 1963
Creator: Garelis, Edward & Meyer, Paul
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Materials Testing Reactor Project Handbook

Description: The following handbook was made for the purpose of: (1) to give a semidetailed description of the testing reactor, and (2) to explain, in so far as possible, the reasons for the design.
Date: May 7, 1951
Creator: Argonne National Laboratory
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Electroplated Metals on Uranium for Aluminum Cladding

Description: Abstract: "Aluminum-clad nickel-plated uranium is corrosion resistant in boiling water. Samples with intentional defects in the aluminum-nickel clodding layers, after testing for more than 300 hr. showed no sign of rapid failure. The study of electroplated metals on uranium for aluminum cladding has defined the effects of several processing variables on the corrosion resistance. The quality of the uranium and the quality of the aluminum-nickel bond were important. Heat treatment and vacuum outg… more
Date: May 4, 1955
Creator: Beach, John G.; Schickner, William C.; Hopkinson, Dolores. & Faust, Charles L.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Li⁶ and Li⁷ (n. 2n) Cross Sections at 14.1 Mev

Description: Abstract: "An absolute measurement of the 14.1-Mev (n, 2n) cross sections of Li-6 and Li-7 has been made using the large scintillator technique, resulting in cross sections in barns of 0.070 +/- 0.006 and 0.056 +/- 0.005 for Li-6 and Li-7, respectively."
Date: May 29, 1958
Creator: Ashby, V. J.; Catron, H. C.; Newkirk, Lester L.; Taylor, C. J. & Williamson, M. A.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Preliminary Appraisal of the Carnotite Resources of the Carrizo Mountains Area, San Juan County, New Mexico, and Apache County, Arizona

Description: From introduction: A rapid appraisal of the carnotite resources of the Salt Wash sandstone member of the Morrison formation in the Carrizo Mountains area was undertaken by the U. S. Geological Survey late in 1951 in connection with its current project of geologic mapping of the area. Though brief and preliminary, this report provides a summary of production trends and estimated reserves in the area and indicates as far as possible the total potential of the area as a source of uranium. This inf… more
Date: May 1952
Creator: Strobell, J. D., Jr.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Design and Feasibility Study of a Pebble Bed Reactor-Steam Power Plant

Description: Originally issued as S and P 1963A, Parts I and II. This report covers a design and feasibility study of a pebble bed reactor-steam power plant of 125 megawatt electrical output. The reactor design which evolved from this study is a two-region thermal breeder, operating on the uranium-thorium cycle, in which all core structural materials are graphite. Fuel is in the form of unclad spherical elements of graphite, containing fissile and fertile material. The primary loop consists of the reactor … more
Date: May 1, 1958
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Equilibrium Dissociation Pressures of the Delta and Epsilon Phases in the Zirconium-Hydrogen System

Description: Abstract: Pressure-temperature isochores were obtained for zirconium-hydrogen alloys, spanning the H/Zr composition range of 1.430 to 1.910. The studies were confined to the temperature limits of 300 to 900ºC, and the pressure limits of 0.01 to 10.0 atm.
Date: May 31, 1964
Creator: Raymond, J. W.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Reactor Containment Design Study

Description: Introduction: Sargent & Lundy was authorized on November 1, 1960, to make an economic and technical feasibility study of various reactor containment designs which are being utilized for several power plants now under construction.
Date: May 18, 1961
Creator: Johnson, R. A. & Nelson, I.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

OMR Degasifier Loop Experiment

Description: Abstract: A loop has been constructed to study the removal of water and highly volatile materials from Organic Moderated Reactor coolant by vacuum degasification. An analysis of the process was made to determine the most important parameters for study during the experimental program.
Date: May 1, 1960
Creator: Corporales, G. W. & Benson, P. R.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

OMRE Fuel Plate Surface Temperature Measurement

Description: Abstract: Accurate measurement of OMRE fuel-element surface temperatures is important for evaluation of the performance of organic compound as moderator and coolant materials in nuclear reactors; a mixture of polyphenyls has been used in reactor operation to-date.
Date: May 1, 1960
Creator: Sudar, S.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Piqua Prototype Handling System

Description: Abstract: Equipment has been developed to handle the fuel elements and control rods for the Piqua (OMR) reactor.With the handling machine, which consists of a shielded cask mounted on a gantry, a fuel element can be replaced in the core in about 27 minutes.
Date: May 1960
Creator: Nadler, H.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
Back to Top of Screen