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  Partner: UNT Libraries Government Documents Department
 Decade: 1960-1969
T = 0 AND T = 1 PAIRING IN LIGHT NUCLEI.

T = 0 AND T = 1 PAIRING IN LIGHT NUCLEI.

Date: January 1, 1969
Creator: Goodman, A. L.
Description: None
Contributing Partner: UNT Libraries Government Documents Department
E-1 common analog model

E-1 common analog model

Date: July 1, 1969
Creator: unknown
Description: None
Contributing Partner: UNT Libraries Government Documents Department
A 5 mechanical test of core support block. Preliminary report

A 5 mechanical test of core support block. Preliminary report

Date: September 30, 1963
Creator: Lee, D. Y.
Description: None
Contributing Partner: UNT Libraries Government Documents Department
10-30 Bev/c ELASTIC SCATTERING OF $pi$$sup +-$+ p, p + p, /anti p/ + p AND K$sup +-$ + p OVER THE /t/ RANGE 0.0005 TO 1 (Bev/c)$sup 2$

10-30 Bev/c ELASTIC SCATTERING OF $pi$$sup +-$+ p, p + p, /anti p/ + p AND K$sup +-$ + p OVER THE /t/ RANGE 0.0005 TO 1 (Bev/c)$sup 2$

Date: July 28, 1964
Creator: Foley, K. J.; Gilmore, R. S.; Jones, R. S.; Lindenbaum, S. J.; Love, W. A.; Ozaki, S. et al.
Description: None
Contributing Partner: UNT Libraries Government Documents Department
A-11 seven cluster model: Phase V, flow induced vibration tests

A-11 seven cluster model: Phase V, flow induced vibration tests

Date: September 29, 1964
Creator: Cherish, P. & Leff, G.J.
Description: None
Contributing Partner: UNT Libraries Government Documents Department
13-WATT CURIUM FUELED THERMOELECTRIC GENERATOR FOR A SIX-MONTH SPACE MISSION. Final Report

13-WATT CURIUM FUELED THERMOELECTRIC GENERATOR FOR A SIX-MONTH SPACE MISSION. Final Report

Date: July 1, 1960
Creator: Bloom, J.L.
Description: None
Contributing Partner: UNT Libraries Government Documents Department
13-WATT CURIUM-FUELED THERMOELECTRIC GENERATOR FOR HARD LUNAR IMPACT MISSION. Final Report-Subtask 5.8

13-WATT CURIUM-FUELED THERMOELECTRIC GENERATOR FOR HARD LUNAR IMPACT MISSION. Final Report-Subtask 5.8

Date: August 1, 1960
Creator: Bloom, J.L.
Description: Results of a conceptual design study for a curium powered thermoelectric generator of minimum size and weight which is capable of sustaining hard impact is presented. The generator produces a minimum of 13 watts of d-c power at 3 volts, and weighs 6.2 pounds excluding shielding. (J.R.D.)
Contributing Partner: UNT Libraries Government Documents Department
14-INCH SWING CHECK VALVE TEST

14-INCH SWING CHECK VALVE TEST

Date: February 10, 1960
Creator: Cygan, R.
Description: The check valve for the Hallam Power Reactor uses a knife-edge bearing for the flapper in place of the usual journal-type bearing. Mechanical cycling in sodium at 600 deg F was used to check operation of this bearing. A total of 309 mechanical cycles was completed with no apparent malfunctioning of the valve. Measured leskage rates were 0.46 gpm at 0.93 psig, 0.73 gpm at 3.4 psig. and 0.32 gpm at 5.9 psig. (M.C.G.)
Contributing Partner: UNT Libraries Government Documents Department
20-ton and 1/2-ton High Explosive Cratering Experiments in Basalt Rock: Final Report, August 1962

20-ton and 1/2-ton High Explosive Cratering Experiments in Basalt Rock: Final Report, August 1962

Date: August 1962
Creator: Vortman, L. J.; MacDougall, H. R. & Rauber, D.F.
Description: From preface: Project Buckboard, a Plowshare sponsored effort, involved the detonation of three 40,000-pound and ten 1000-pound high-explosive charges in basalt rock.
Contributing Partner: UNT Libraries Government Documents Department
20-ton HE Cratering Experiments in Desert Alluvium: Final Report, May 1962

20-ton HE Cratering Experiments in Desert Alluvium: Final Report, May 1962

Date: March 1960
Creator: Vortman, Luke J. & MacDougall, H. R.
Description: From abstract and summary: Project Stagecoach consisted of the detonation of three 40,000-pound charges. Blocks of cast TNT were stacked to resemble a sphere and, the whole center-detonated.
Contributing Partner: UNT Libraries Government Documents Department
30 Megawatt Heat Exchanger and Steam Generator for Sodium Cooled Reactor System

30 Megawatt Heat Exchanger and Steam Generator for Sodium Cooled Reactor System

Date: January 31, 1962
Creator: unknown
Description: Final design for the 30 megawatt intermediate heat exchanger and steam generator.
Contributing Partner: UNT Libraries Government Documents Department
30 Megawatt Heat Exchanger and Steam Generator for Sodium Cooled Reactor System: Volume 2, Chemical and Stress Analysis

30 Megawatt Heat Exchanger and Steam Generator for Sodium Cooled Reactor System: Volume 2, Chemical and Stress Analysis

Date: February 28, 1962
Creator: unknown
Description: Chemical engineering analysis and stress analysis for design of the 3 megawatt intermediate heat exchanger and steam generator for service with a liquid sodium heat transfer fluid.
Contributing Partner: UNT Libraries Government Documents Department
30 Megawatt Heat Exchanger and Steam Generator for Sodium Cooled Reactor System: Volume 4, Operation and Maintenance Procedures

30 Megawatt Heat Exchanger and Steam Generator for Sodium Cooled Reactor System: Volume 4, Operation and Maintenance Procedures

Date: May 15, 1962
Creator: unknown
Description: Operation and maintenance procedures for 30 megawatt heat exchanger and steam generator for sodium cooled reactor system.
Contributing Partner: UNT Libraries Government Documents Department
40-MW(E) PROTOTYPE HIGH-TEMPERATURE GAS-COOLED REACTOR. RESEARCH AND DEVELOPMENT PROGRAM. Quarterly Progress Report for the Period Ending March 31, 1963

40-MW(E) PROTOTYPE HIGH-TEMPERATURE GAS-COOLED REACTOR. RESEARCH AND DEVELOPMENT PROGRAM. Quarterly Progress Report for the Period Ending March 31, 1963

Date: October 31, 1964
Creator: unknown
Description: None
Contributing Partner: UNT Libraries Government Documents Department
40-MW(E) PROTOTYPE HIGH-TEMPERATURE GAS-COOLED REACTOR RESEARCH AND DEVELOPMENT PROGRAM. Summary Report for the Period January 1, 1959-December 31, 1959 and Quarterly Progress Report for the Period October 1, 1959-December 31, 1959

40-MW(E) PROTOTYPE HIGH-TEMPERATURE GAS-COOLED REACTOR RESEARCH AND DEVELOPMENT PROGRAM. Summary Report for the Period January 1, 1959-December 31, 1959 and Quarterly Progress Report for the Period October 1, 1959-December 31, 1959

Date: September 1, 1960
Creator: unknown
Description: The HTGR prototype plant (Peach Bottom Power Reactor) is being designed to produce steam at l450 psi and 1000 deg F and to have a net capacity of 40 Mw(e). The fuel temperatures and gas pressures will be approximately the same as those required for larger plants. The reactor data and operating conditions for the graphite-clad core are given. The reactor and primary coolant systems are described. The prospects for development of the graphite-clad fuel element in time for use in the first loading of the reactor were improved by important advances in methods of fabrication and testing of both fuel compacts and graphite sleeves. The hot-pressing process for making fuel compacts was used successfully to make full-size compacts with a uniform distribution of ThC/sub 2/- UC/sub 2/ particles. Three irradiation capsules were fabricated and inserted in a test reactor to determine fuel compact and sleeve performance under HTGR conditions of irradiation and temperature. Two of these ran satisfactorily for the scheduled time of operation. A scope design study of the in-pile loop that will be used to evaluate the full-diameter graphite-clad element was completed. Experiments to determine the extent of fuel migration within the element were undertaken. Preliminary results ...
Contributing Partner: UNT Libraries Government Documents Department
100-WATT CURIUM-242 FUELED THERMOELECTRIC GENERATOR--CONCEPTUAL DESIGN. SNAP Subtask 5.7 Final Report

100-WATT CURIUM-242 FUELED THERMOELECTRIC GENERATOR--CONCEPTUAL DESIGN. SNAP Subtask 5.7 Final Report

Date: May 1, 1960
Creator: Weddell, J.B. & Bloom, J.
Description: A thermoelectric generator which produces 100 watts of electrical power continuously over a six-month operational life in a space environment was designed. It employs the heat produced by the decay of Cm/sup 24/ as the source of power. Uniform output over the operational life of the generator is accomplished by means of a thermally actuated shutter which maintains the hot junction temperature of the thermoelectric conventer at a constunt figure by varying the amount of surplus heat which is radiated directly to space from the heat source. The isotopic heat source is designed to safely contain the Cm/sup 242/ under conditions of launch pad abont and rocket failure, but to burn up upon re-entry to the earth's atmosphere from orbital velocity. (W.L.H.)
Contributing Partner: UNT Libraries Government Documents Department
I-131 in milk from Cabriolet fallout

I-131 in milk from Cabriolet fallout

Date: March 31, 1966
Creator: Tamplin, A.
Description: No abstract available.
Contributing Partner: UNT Libraries Government Documents Department
200-Mwe Prototype Large SGR: Reactor Structure Design and Evaluation

200-Mwe Prototype Large SGR: Reactor Structure Design and Evaluation

Date: 1965
Creator: North American Aviation. Atomics International Division.
Description: From abstract: This document presents the reactor structure design and evaluation for a 200-Mwe prototype large SGR.
Contributing Partner: UNT Libraries Government Documents Department
300,000-KWE SGR Nuclear Power Plant of Current Technology

300,000-KWE SGR Nuclear Power Plant of Current Technology

Date: August 1, 1960
Creator: Renard, J.; Peckinpaugh, C. L. & Aronstein, R. E.
Description: Abstract: This report describes a 300,000-kwe, sodium-cooled, graphite-moderated nuclear power plant based on existing technical information.
Contributing Partner: UNT Libraries Government Documents Department
EEN-307, Irradiation of units at low temperature test

EEN-307, Irradiation of units at low temperature test

Date: April 13, 1960
Creator: Guthrie, J.B.
Description: EWR-ESE-144, Fifty MC-890 type final assemblies were subjected to irradiation at low temperature test in order to determine if irradiation would reduce the frequency of high voltage breakdowns. A control lot of a like number of units was subjected to low temperature test in the same manner except without irradiation.
Contributing Partner: UNT Libraries Government Documents Department
EN-318 evaluation of slow warm-up through special test of MC-890 type power supplies

EN-318 evaluation of slow warm-up through special test of MC-890 type power supplies

Date: September 1, 1960
Creator: Ling, R.F.
Description: ESE-171: This EN run was made to determine if there is any relationship between the H-5 transistor electrical characteristics, the assembly processes, and slow warm-up of the MC-890 Power Supply. Included is the test data on the H-5 transistors and the results of the High Temperature Life Test (185 {degrees}F) of 380 MC-890 Power Supplies.
Contributing Partner: UNT Libraries Government Documents Department
EEN-333, revised getter flash procedure

EEN-333, revised getter flash procedure

Date: June 28, 1960
Creator: Brown, W.C.
Description: EWR No. VTE-188--Tubes processed by flashing getters immediately prior to seal-off from vacuum systems are compared for total residual gas pressure to tubes processed by flashing getters after tubes were sealed off vacuum systems. Comparisons of residual pressures determined from current flows in the cold cathode ion gauge.
Contributing Partner: UNT Libraries Government Documents Department
500-THGC--A 500 NODE TRANSIENT HEAT TRANSFER CODE

500-THGC--A 500 NODE TRANSIENT HEAT TRANSFER CODE

Date: March 27, 1964
Creator: Blaine, R.A. & Berland, R.F.
Description: None
Contributing Partner: UNT Libraries Government Documents Department
A 1000 HOUR TEST OF A CORROSION PRODUCT SEPARATOR UNIT IN A HAYNES ALLOY NO. 25 LOOP CONTAINING MERCURY--TEST G-16

A 1000 HOUR TEST OF A CORROSION PRODUCT SEPARATOR UNIT IN A HAYNES ALLOY NO. 25 LOOP CONTAINING MERCURY--TEST G-16

Date: March 1, 1962
Creator: Nejedlik, J.F.
Description: One of the major unsolved problems affecting the life of the SNAP II Power Conversion System is the mass transfer of corrosion products by mercury and subsequent deposition. It is feared that the corrosion products might tend to accumulate in critical areas such as orifices, bearings and so forth. Therefore, this test was conducted to evaluate a corrosion product separator and to determine the influence of corrosion product removal on corrosion rate. The corrosion product separator was successful in removing 85 percent of the elements corroded from the container walls. The loop and separator, both fabricated from Haynes alloy No. 25, operated for 1000 hours. The mercury was boiled and condensed at 1100 deg F, superheated to 1190 deg F and subcooled to 325 deg F. The flow rate in this loop was much higher than in previous loops, being approximately 37 pounds of mercury per hour as contrasted with approximately l2 pounds of raercury per hour. No increase in corrosion rate was noticed as a result of the higher flow rates and velocity or by the removal of corrosion products. If this type of separator or an improved type works equally as well in the final application, the danger ...
Contributing Partner: UNT Libraries Government Documents Department
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