Serial/Series Title
Decade
Month
12 Matching Results
Results open in a new window/tab.
Results:
1 - 12 of
12
A Conceptual Design of a Thorium-Uranium (233) Power Breeder Reactor
From abstract: A conceptual design study has been performed for a sodium cooled, graphite moderated, thermal power-breeder reactor utilizing the Thorium-Uranium 233 breeding cycle. Several aspects of the design of the system are considered but no attempt has been made to supply all the details. It appears that the design presented is feasible and will allow the production of economic power as well as full utilization of thorium resources.
Date:
February 1, 1954
Creator:
Henrie, J. O. & Weisner, E. F.
System:
The UNT Digital Library
Organic Moderated Reactor Experiment : Safeguards Summary
Abstract: This report presents a description of the Organic Moderated Reactor Experiment (OMRE), of the hazards associated with this experiment, and all of the safeguards taken to ensure the safety of the operating personnel and the population of the surrounding area.
Date:
February 1, 1958
Creator:
Sletten, H. L. & Blue, L. R.
System:
The UNT Digital Library
Experimental Evaluation of a Sodium-to-Sodium Heliflow Heat Exchanger at Temperatures up to 1200°F
Abstract: Because of the outstanding heat transfer efficiency of sodium, it is necessary in sodium-cooled reactors to consider and attempt to prevent the occurrence of adverse stresses as a result of thermal transients in the system.
Date:
February 28, 1961
Creator:
McDonald, J. S.
System:
The UNT Digital Library
Operation and Analysis of a 3000 KW Liquid Metal Model Steam Generator
Abstract: A 3000 kw (thermal) bayonet duplex tube model steam generator was performance-tested in a liquid metal test loop at MSA Research Corporation, Callery, Pennsylvania, under the cognizance of Atomics International.
Date:
February 28, 1961
Creator:
Webster, L. J.
System:
The UNT Digital Library
Design Modifications to the SRE during FY 1960
Abstract: The means to prevent the recurrence of tetralin leakage into the SRE sodium systems are discussed. Included is a description of the redesign of system components to utilize alternate coolants such as nitrogen, air, and NaK.
Date:
February 15, 1961
Creator:
Deegan, G. E.; Dermer, M. D.; Flanagan, J. S.; Gower, G. C.; Hall, R. J.; Hinze, R. B. et al.
System:
The UNT Digital Library
Irradiation Swelling, Phase Reversion, and Intergranular Cracking of U-10 wt % Mo Fuel Alloy
Abstract: A fuel development program has been conducted, to investigate the behavior of U-10 wt% Mo alloy at the fission rates and temperatures anticipated in Core I of the Hallam Nuclear Power Facility.
Date:
February 1, 1965
Creator:
Willard, R. M. & Schmitt, A. R.
System:
The UNT Digital Library
The NAA 47 U - 10 Mo Fuel Irradiation Program for HNPF Core 1
Abstract: Atomics International conducted a fuel irradiation program to investigate and define the behavior of U-10 Mo fuel at the temperatures and fission rates anticipated in Hallam Nuclear Power Facility (HNPF) Core I.
Date:
February 1, 1965
Creator:
Schmitt, A. R.; Willard, R. M. & Magnus, D. K.
System:
The UNT Digital Library
Performance of Cesium Thermionic Diodes Operated in Series-Parallel Circuits
Introduction: The purpose of this experiment is to determine the loss of electrical power output due to operating many unequally-heated cesium diodes, connected in series and parallel circuits.
Date:
February 1, 1963
Creator:
Holland, J. W.
System:
The UNT Digital Library
Final Design of Sodium-Heated, Modular, Steam Generators for the SCTI
Abstract: The following report covers the final design of the modular steam generators.
Date:
February 1, 1965
Creator:
Casey, D. F.; Hammer, J. J.; Logan, D. & Williams, M. C.
System:
The UNT Digital Library
Flux Control for Irradiation Experiments
Abstract: This report reviews various means which have been used to control experimental conditions in irradiation experiments, and presents the concept of local flux control.
Date:
February 1, 1965
Creator:
McCarty, W. K.
System:
The UNT Digital Library
Application of Nuclear Power Plants (SNAP Units) to the Manned Orbiting Research Laboratory (MORL)
Abstract: This report describes in detail two designs of a nominal 6-kwe Nuclear Power Plant (NPP), one using thermoelectrics for power conversion and the other using the Mercury-Rankine cycle NPP.
Date:
February 1, 1965
Creator:
Botts, W. V.; Marko, M.; McCourt, P. E.; Keshishian, V.; Piccot, A. R. & Budney, G. S.
System:
The UNT Digital Library
Fatigue Characteristics of 37-Tube, Modular, Steam Generator Head
Abstract: This report presents the pertinent results of a series of fatigue tests relating to the evaporator and superheater 37-tube module heads for the sodium heated steam generator described in NAA-SR-9826.
Date:
February 20, 1965
Creator:
Lemcoe, M. M.
System:
The UNT Digital Library