Serial/Series Title
Country
56 Matching Results
Results open in a new window/tab.
Results:
1 - 24 of
56
next
Carbide Fuels in Fast Reactors
Abstract: Cladding and fuel material processing prospects are reviewed, and fuel system possibilities for near-term (~1 mill/kwh) and long-range (<0.5 mil/kmh) fuel cycles are described.
Date:
September 15, 1965
Creator:
Wheelock, C. W.
System:
The UNT Digital Library
Piqua Nuclear Power Facility Operations Analysis Program Progress Report Number 5: July-December 1964
Progress report for the Piqua Reactor Operations Analysis Program describing observations and analyses at the Piqua Nuclear Power Facility (PNPF). The program goals are to monitor operations and collect data in order to ensure that the plant's operation is safe, to improve design and performance, to evaluate the performance and lifetime of the plant's components and systems, to evaluate plant safety and safeguards, and to disseminate all information to the scientific community.
Date:
June 15, 1965
Creator:
unknown
System:
The UNT Digital Library
SNAP 10A FSEM-3 Agena Compatibility Test
From abstract: This report summarizes the results of SNAP-10A/Agena developmental testing and final vehicle systems tests.
Date:
June 15, 1965
Creator:
Teresa, M.
System:
The UNT Digital Library
Piqua Nuclear Power Facility Operations Analysis Program Progress Report Number 4: January-June 1964
Progress report for the Piqua Reactor Operations Analysis Program describing observations and analyses at the Piqua Nuclear Power Facility (PNPF). The program goals are to monitor operations and collect data in order to ensure that the plant's operation is safe, to improve design and performance, to evaluate the performance and lifetime of the plant's components and systems, to evaluate plant safety and safeguards, and to disseminate all information to the scientific community.
Date:
December 15, 1964
Creator:
Cole, H. S.; Hausknecht, D. F.; Jenkins, O. G., Jr.; Lew, D. E.; Mandel, H.; Pearson, E. N. et al.
System:
The UNT Digital Library
Analysis of Stresses in Bellows
Abstract: Design charts and systematic design forms are presented for simplified calculations to check the number of convolutions and thickness required to limit the deflection and pressure stress range in three types of bellows.
Date:
October 15, 1964
Creator:
Anderson, W. F.
System:
The UNT Digital Library
Boiling Studies for Sodium Reactor Safety: Part 2, Pool Boiling and Initial Force Convection Tests and Analyses
Abstract: In fulfillment of the general objective of developing information on two-phase flow required in the safety evaluation of sodium cooled reactors, pool and forced-convection boiling of sodium were studied both experimentally and analytically.
Date:
October 15, 1964
Creator:
Lurie, H. & Noyes, R. C.
System:
The UNT Digital Library
Design of an Experimental Bowable Fuel Element for the SRE
Abstract: An experimental bowable fuel element was developed to study temperature oscillations in the second core loading of the SRE.
Date:
October 15, 1964
Creator:
Peckinpaugh, C. L.
System:
The UNT Digital Library
Evaluation of Coolant Impurity Removal Equipment at the OMRE
Abstract: The experimental application of centrifugal clarification, precoat filtration, conventional filtration, and adsorption to the removal of impurities from a bypass stream of irradiated reactor coolant at the Organic Moderated Reactor Experiment is described and evaluated.
Date:
October 15, 1964
Creator:
Barbour, P. & Davis, W. W.
System:
The UNT Digital Library
Radiolysis Products of Polyphenyl Coolants: Part 3, Omre High Boilers
Abstract: The nature of the high boiling radiolysis products of OMRE coolants was studied extensively.
Date:
October 15, 1964
Creator:
Keen, R. T.; Orr, W. L.; Miller, L. J.; Sullivan, R. J. & Shepard, R. C.
System:
The UNT Digital Library
Hallam Nuclear Power Facility, Reactor Operations Analysis Program: Semiannual Progress Report Number 3, September 1963-February 1964
From introduction: This report provides industry, plant operators, and the scientific community with information covering the results of the performance analysis.
Date:
September 15, 1964
Creator:
Darley, D. K.
System:
The UNT Digital Library
Stress and Elevated Temperature Fatigue Characteristics of Large Bellows
From abstract: Charts in this report show axial stress distribution over exterior bellows surfaces induced by bellows axial deflection, and by internal pressurization. The influence of root rings on stress distribution is presented graphically.
Date:
September 15, 1964
Creator:
Winborne, R. A.
System:
The UNT Digital Library
Piqua Nuclear Power Facility Operations Analysis Program Progress Report Number 3: July-December 1963
Progress report for the Piqua Reactor Operations Analysis Program describing observations and analyses at the Piqua Nuclear Power Facility (PNPF). The program goals are to monitor operations and collect data in order to ensure that the plant's operation is safe, to improve design and performance, to evaluate the performance and lifetime of the plant's components and systems, to evaluate plant safety and safeguards, and to disseminate all information to the scientific community.
Date:
July 15, 1964
Creator:
Auleta, J. J.
System:
The UNT Digital Library
SNAP 10A-PSM-1: Test Results
Introduction: On November 14, 1961, an environmental test program commenced on the first SNAP 10A system structure, S10A-PSM-1.
Date:
July 15, 1964
Creator:
Oliva, R. M.
System:
The UNT Digital Library
SNAP 10A Structural Analysis
Abstract: this report discusses and summarizes all stress analysis done on the SNAP 10A system; it also mentions many of the structural tests which were accomplished.
Date:
July 15, 1964
Creator:
Boulanger, J. R.
System:
The UNT Digital Library
Structural Test on the Final SNAP 10A Prototype System
Abstract: This report presents the results of the structural tests which were performed on the S10A-PSM-1A system to qualify the basic structural design for the anticipated launch environment.
Date:
July 15, 1964
Creator:
Henley, H. L. & Dauterman, W. H.
System:
The UNT Digital Library
Analog Models for HNPF Control and Protection Studies
Abstract: This report, intended as a working document, contains analytic representations and analog models of the Hallam Nuclear Power Facility as used in studies of the Control and Protection Systems.
Date:
June 15, 1964
Creator:
Dunsmore, C. L.
System:
The UNT Digital Library
HNPF Control System Response During Transient Conditions
Abstract: This report documents the results of power ramps inposed on the HNPF during the month of January 1964.
Date:
June 15, 1964
Creator:
Shaw, P. F.
System:
The UNT Digital Library
Operating Experience with Heat Transfer System Pumps at the Hallum Nuclear Power Facility
Introduction: It is the purpose of this report to describe the operating and maintenance experience obtained at HNPF on the sodium heat transfer pumps.
Date:
June 15, 1964
Creator:
Durand, R. E.
System:
The UNT Digital Library
QUICKIE: A Computer Program for Spatially Independent Multigroup Slowing-Down and Thermalization Calculations
Introduction: QUICKIE is a computer program designed to solve the multigroup neutron slowing down and thermalization equations without consideration of spatial dimensions.
Date:
April 15, 1964
Creator:
Boling, M. & Rhoades, W.
System:
The UNT Digital Library
Dynamic Void Fraction Measurement System
Abstract: Various methods and techniques of measuring void fractions in boiling heat transfer media are discussed.
Date:
May 15, 1963
Creator:
Kendron, J. H.; Stoner, E. E. & Taylor, G. M.
System:
The UNT Digital Library
Capsule Irradiation of Unalloyed Uranium at High Temperatures
Abstract: Cast and Wrought specimens and restrained wrought specimens of unalloyed uranium were irradiated in the Materials Testing Reactor, as the first in a series of experiments to develop fuel materials for sodium cooled reactors.
Date:
August 15, 1962
Creator:
Harrington, D. G. & Newton, J. B.
System:
The UNT Digital Library
The FAIM Code: a Multigroup, One-Dimensional Diffusion Equation Code
Abstract: FAIM is a general multigroup, one-dimensional diffusion equation code programmed in FORTRAN language for the IBM 7090 computer.
Date:
April 15, 1962
Creator:
Baller, D. C.
System:
The UNT Digital Library
Metallurgical Aspects of SRE Fuel Element Damage Episode
Abstract: An investigation of the metallurgical aspects of the SRE fuel element episode, that occurred July 26, 1959, has been completed.
Date:
October 15, 1961
Creator:
Ballif, J. L.
System:
The UNT Digital Library
Coolant Flow and Outlet Temperature: Computer-Monitors for the Hallam Nuclear Power Facility Plant Protective System
Abstract: The design and application of two computers for the HNPF protective system is discussed.
Date:
September 15, 1961
Creator:
Schlein, H.
System:
The UNT Digital Library