815 research outputs found
Portrait of Charles Boyd as "The Snob" in the Borovansky Ballet's production of "La Boutique fantasque" [picture] /
Condition: Good.; Title from accompanying documentation, see file 203/02/00408.; Artist's signature: "Enid T.L. Dickson 1951 [date indistinct, possibly 1957]"--Lower right.; Also available online at: http://nla.gov.au/nla.pic-an24130627
Specialty farming in Idaho: Selecting a site
Bulletin no. 744 Moscow, Idaho :University of Idaho, College of Agriculture, Cooperative Extension System, 1992-10-01. Author(s): Barney, D.L.; Finnerty, T.L.; Mancuso, C.J
Specialty farming in Idaho: Is it for me?
Bulletin no. 743 Moscow, Idaho :University of Idaho, College of Agriculture, Cooperative Extension System, 1992-01-01. Author(s): Barney, D.L.; Finnerty, T.L. ; Laughlin, K.M
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Folio of the Tempe Quadrangle, Arizona
This GI folio comprises a suite of environmental geology maps for the Tempe Quadrangle of Maricopa County, Arizona. Author order varies from map to map, but always comprises T.L. Pewe, C.S. Wellendorf and J.T. Bales. There are 8 maps in total, all maps are at 1:24,000 map scale.Documents in the AZGS Document Repository collection are made available by the Arizona Geological Survey (AZGS) and the University Libraries at the University of Arizona. For more information about items in this collection, please contact [email protected]
Notes on the History of the Sale Room of the Egyptian Museum in Cairo
The author retraces the history of the Sale Room of the Cairo Museum, from the first sales at the Boulaq Museum to the more organised ones at the Giza Museum, up to the Sale Room of the Cairo Museum, still exhisting at the beginning of the 1970s. This latter date is attested by some pages of the Register of the Sale Room, of which some photographs are preserved in the Archives of the Statale University of Milan. The supervisors of the Sale Room through the years are presented, as well as some case studies, including the gifts of State
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(Safety and reliability of nuclear power plant technology)
The traveler attended the 16th MPA Seminar on the Safety and Reliability of Plant Technology with Special Emphasis on Nuclear Technology. The objective of the trip was to gather information and data that could prove useful to the US Nuclear Regulatory Commission (USNRC) sponsored Heavy-Section Steel Irradiation (HSSI) and Heavy-Section Steel Technology (HSST) Programs and to present a paper entitled, Effects of Irradiation on Initiation and Crack-Arrest Toughness of Two High-Copper Welds and on Stainless Steel Cladding. This paper summarizes results from the 5th, 6th, and 7th Irradiation Series of experiments performed within the HSSI Program by the Metals and Ceramics Division at Oak Ridge National Laboratory (ORNL)
An Overview of FAVOR: A fracture analysis computer code for nuclear reactor pressure vessels
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Potential effect of fracture technology on IPTS (Integrated Pressurized Thermal Shock) analysis (Fracture toughness: K sub la and K sub lc and warm prestressing)
A major nuclear plant life extension issue to be confronted in the 1990's is pressure vessel integrity for the pressurized thermal shock (PTS) loading condition. Governing criteria associated with PTS are included in The PTS Rule'' (10 CFR 50.61) and Regulatory Guide 1.154: Format and Content of Plant-Specific Pressurized Thermal Shock Safety Analysis Reports for Pressurized Water Reactors. The results of the Integrated Pressurized Water Reactors. The results of the Integrated Pressurized Thermal Shock (IPTS) Program, along with risk assessments and fracture analyses performed by the NRC and reactor system vendors, contributed to the derivation of the PTS Rule. Over the last several years, the Heavy Section Steel Technology (HSST) Program at the Oak Ridge National Laboratory (ORNL) has performed a series of large-scale fracture-mechanics experiments. The Thermal Shock Experiments (TSE), Pressurized Thermal Shock Experiments (PTSE), and Wide Plate Experiments (WPE) produced K{sub IC} and K{sub Ia} data that suggest increased mean K{sub IC} and K{sub Ia} curves relative to the ones used in the IPTS study. Also, the PTSE and WPE have demonstrated that prototypical nuclear reactor pressure vessel steels are capable of arresting a propagating crack at K{sub I} values considerably above 220 MPa{radical}m, the implicit limit of the ASME Code and the limit used in the IPTS studies. This document provides a discussion of the results of these experiments
to T.L. Treadwell, 24 November 1844
https://egrove.olemiss.edu/aldrichcorr_b/1076/thumbnail.jp
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