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Annual Technical Progress Report, AEC Unclassified Programs: Fiscal Year 1968
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
Creator:
unknown
System:
The UNT Digital Library
Quarterly Technical Progress Report, AEC Unclassified Programs: Fiscal Year 1968
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
Creator:
unknown
System:
The UNT Digital Library
Piqua Nuclear Power Facility Operations Analysis Program Progress Report Number 9: 1966
The following progress report describes the examination of elements removed in comparison to a previous study on the power facility reactor operations.
Date:
May 1969
Creator:
North American Aviation. Atomics International Division.
System:
The UNT Digital Library
Safety Evaluation of PNPF Modifications
"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.
System:
The UNT Digital Library
Equilibrium Dissociation Pressures of the Delta and Epsilon Phases in the Zirconium-Hydrogen System
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.
System:
The UNT Digital Library
SNAP 2: Structural and Dynamic Analysis
Abstract: The structural design criteria and the system basic loads for the SNAP 2 compact power unit are presented.
Date:
May 1, 1964
Creator:
Castle, R. 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
Investigations of Neutron Penetration in TiH and Steel Slabs
Abstract: A multigroup P1 approximation for hydrogen scattered neutrons has been developed and applied to the study of neutron flux distributions in titanium hydride and steel shield systems.
Date:
May 15, 1961
Creator:
Karcher, R. H.
System:
The UNT Digital Library
OMR Degasifier Loop Experiment
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.
System:
The UNT Digital Library
OMRE Fuel Plate Surface Temperature Measurement
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.
System:
The UNT Digital Library
Piqua Prototype Handling System
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.
System:
The UNT Digital Library
Plutonium: Enriched OMR Cores
Abstract: The influence of plutonium on the nuclear characteristics of organic moderated cores is studied.
Date:
May 1, 1960
Creator:
Connolly, T. J.
System:
The UNT Digital Library
Thermal Cycling and Leakage Tests of 12-inch Valves for Sodium Service
Abstract: Tests were performed to determine the effect of thermal cycling on the across-the-seat leakage characteristics of commercially available valves considered for use in the sodium coolant system of the Hallam Nuclear Power Facility.
Date:
May 1, 1960
Creator:
Baroczy, C. J.
System:
The UNT Digital Library