Resource Type

Piqua Nuclear Power Facility Operations Analysis Program Progress Report Number 2: 1963 (open access)

Piqua Nuclear Power Facility Operations Analysis Program Progress Report Number 2: 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: November 30, 1963
Creator: Auleta, J. J.
System: The UNT Digital Library
Defense Authorization and Appropriations Bills: FY1961-FY2019 (open access)

Defense Authorization and Appropriations Bills: FY1961-FY2019

This report is a research aid that lists the U.S. Department of Defense (DOD) authorization and appropriations bills for FY1961-FY2019 including: bill numbers, report numbers, dates reported and passed, recorded vote numbers and vote tallies, dates of passage of the conference reports with their numbers and votes, vetoes, substitutions, dates of final passage, and public law numbers. Significant definitions are also included.
Date: November 27, 2018
Creator: DeBruyne, Nese F. & Torreon, Barbara Salazar
System: The UNT Digital Library
Annual Progress Report on Fuel Element Development for Yy 1963 (open access)

Annual Progress Report on Fuel Element Development for Yy 1963

Progress in fuels and materials development is reported. Irradiation tests on powdered UAl/sub 3/ intermetallic compounds demonstrated good stability and fission gas retention capabilities. Developmental aluminum powder metal products showed good corrosion resistance at high temperatures while retaining excellent high temperature strength. All of the fuel compositions tested (UO/sub 2/, U/sub 3/O/sub 8/, and UAl/sub 3/ in aluminum matrices) exhibited density decreases under irradiation. Tensile tests on sandwich-type fuel plates at elevated temperatures indicated that the fuel plate strength is strongly influenced by the core material rather than dependent primarily on the cladding material as was found true of lower (MTR) temperatures. Three capsules containing beryllium were inserted in the ETR, in order to determine strength, gas release, and growth during a high-temperature (600--800 deg C) irradiation. An MTR fuel element employing advanced metallurgical techniques to optimize the hydraulic and heat transfer characteristics was fuily irradiated in the MTR. The fuel element consisted of 32 plates containing 250 g U/sup 235/ in a U/sub 3/O/ sub 8/--Al dispersion. A prototype ETR fuel element was made without side plates. (M.C.G.)
Date: November 25, 1963
Creator: Gibson, G. W.; Graber, M. J. & Francis, W. C.
System: The UNT Digital Library