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High heat flux heater development status report
The development of a high heat flux heater for use in corrosion rate and stress-rupture tests of fuel cladding materials in a sodium environment is described.
Date:
June 15, 1968
Creator:
McKisson, R. L. & Babbe, E. L.
System:
The UNT Digital Library
Ionium Recovery Plant Design Report: Topical Report
This report documents the study of the recovery of thorium by solvent extraction in pilot plant pulse columns, using a filtered liquor from nitric acid digestions of the raffinate cake produced by the ethyl ether extraction of uranium from pitchblende.
Date:
April 15, 1959
Creator:
Edwards, R. M.; Fariss, R. H. & Werkema, R. G.
System:
The UNT Digital Library
Evaluation and Consolidation of Electrolytic Thorium
Abstract: "Sound, fabricable ingots of thorium were produced by triple are melting of electrolytic thorium. Consumable electrodes were fabricated by tack welding of cold-pressed and vacuum-sintered bars of the granular thorium electrodeposited from a molten-salt bath. The hydrogen content of the electrodeposited material was reduced from 80 to 4 ppm by vacuum sintering at 1250 C at pressures below 1 x 10-(-3) mm of mercury. Both sodium and chlorine content were reduced during melting; sodium from 250 to 25 ppm and chlorine from 1000 to 30 ppm. Oxygen and HCl acid-insoluble contents increased during sintering and melting. Oxygen content increased from 0.35 to 0.50 w/o and HCl acid-insoluble content from 0.8 to 4.0 w/o. A starlike includion revealed by metallographic examination of the as-cast thorium was identified as ThO2."
Date:
June 15, 1955
Creator:
Saller, Henry A.; Dickerson, Ronald F. & Foster, Ellis L.
System:
The UNT Digital Library
ABWR: PL-2 Design Report
From preface: This report satisfies the quarterly progress report requirements for PL-1 and PL-2 plant design work for the period ending September 30, 1960 At present time a SL-1 Core 2 is under construction. This is a replacement core for SL-1 (ALPR) and will be identical to a PL-2 core; a PL condenser is under test at the SL-1 facility; final construction plans for PL components and modules which are not site sensitive will be completed in March 1961.
Date:
October 15, 1960
Creator:
Combustion Engineering, inc. Nuclear Division.
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
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
Basic Chemistry of High Temperature Inorganic Systems, Semiannual Progress Report: July-December 1956
From abstract: The vapor pressure determination of solid ThF4 has been completed. Experiments to determine the heat of formation of ThF4 by studying the reaction of ThF4 with SiO2 are described.
Date:
July 15, 1957
Creator:
Yosim, S. J. & Milne, T. A.
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
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
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
Organic Moderated Reactor Experiment Progress Report: October 1955-July 1956
Report describing technical progress on the design and construction of an Organic Moderated Reactor Experiment (OMRE), to be operated at the National Reactor Testing Station in Arco, Idaho. "This is the first report of the series and coves the period from the initiation of the project to July 31, 1956. Also included as an appendix to the report is a detailed description of the OMRE facility" (p. 3).
Date:
March 15, 1957
Creator:
Trilling, C. A.
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
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
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
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
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
Reactor Safety Quarterly Progress Report: May-July 1956
From abstract: Impact tests on the Mark III Hanford safety element indicate that the design is mechanically adequate and does not constitute a personnel hazard.
Date:
March 15, 1957
Creator:
Miller, N. C.
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
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
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
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
Mechanical Properties of Zircaloy-2 Weld Metal
Abstract: Zircaloy-2 weld metal, obtained by inert gas non-consumable-electrode welding, was subjected to tensile, strain fatigue, and creep-rupture testing.
Date:
April 15, 1961
Creator:
Beitscher, S.
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