Advanced Gas Cooled Nuclear Reactor Materials Evaluation and Development Program. Progress report, January 1, 1980-March 31, 1980
Description
Results are presented of work performed on the Advanced Gas-Cooled Nuclear Reactor Materials Evaluation and Development Program. The objectives of this program are to evaluate candidate alloys for Very High Temperature Reactor (VHTR) Nuclear Process Heat (NPH) and Direct Cycle Helium Turbine (DCHT) applications, in terms of the effect of simulated reactor primary coolant (helium containing small amounts of various other gases), high temperatures, and long time exposures, on the mechanical properties and structural and surface stability of selected candidate alloys. A second objective is to select and recommend materials for future test facilities and more extensive qualification programs. Included … continued below
Physical Description
100 pages
Creation Information
Creator: Unknown. June 25, 1980.
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This report is part of the collection entitled: Office of Scientific & Technical Information Technical Reports and was provided by the UNT Libraries Government Documents Department to the UNT Digital Library, a digital repository hosted by the UNT Libraries. It has been viewed 43 times. More information about this report can be viewed below.
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General Electric Co., Schenectady, NY (USA). Energy Systems Programs Dept.
Place of Publication: United States
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Description
Results are presented of work performed on the Advanced Gas-Cooled Nuclear Reactor Materials Evaluation and Development Program. The objectives of this program are to evaluate candidate alloys for Very High Temperature Reactor (VHTR) Nuclear Process Heat (NPH) and Direct Cycle Helium Turbine (DCHT) applications, in terms of the effect of simulated reactor primary coolant (helium containing small amounts of various other gases), high temperatures, and long time exposures, on the mechanical properties and structural and surface stability of selected candidate alloys. A second objective is to select and recommend materials for future test facilities and more extensive qualification programs. Included are the activities associated with the status of the simulated reactor helium supply system, testing equipment and gas chemistry analysis instrumentation and equipment. The progress in the screening test program is described, including screening creep results and metallographic analysis for materials thermally exposed or tested at 750, 850, and 950/sup 0/C.
Physical Description
100 pages
Notes
NTIS, PC A05/MF A01.
Subjects
Keywords
- Alloy-Hd-556
- Alloy-Hk-40
- Alloy-In-519
- Alloy-In-738
- Alloy-Mm-0011
- Alloy-Mo-Re-2
- Alloy-Nx-188
- Alloy-Tzm
- Alloys
- Aluminium Alloys
- Boron Additions
- Boron Alloys
- Carbon Additions
- Chromium Alloys
- Chromium Base Alloys
- Cobalt Alloys
- Corrosion Resistance
- Corrosive Effects
- Creep
- Cryogenic Fluids
- Elements
- Fluids
- Gas Cooled Reactors
- Graphite Moderated Reactors
- Hastelloy X
- Hastelloys
- Heat Resistant Materials
- Heat Resisting Alloys
- Helium
- Htgr Type Reactors
- Incoloy 800
- Incoloy 802
- Incoloy Alloys
- Inconel 617
- Inconel 713Lc
- Inconel Alloys
- Iron Alloys
- Iron Base Alloys
- Manaurite 36X
- Manganese Alloys
- Materials
- Mechanical Properties
- Molybdenum Alloys
- Molybdenum Base Alloys
- Nickel Alloys
- Nickel Base Alloys
- Niobium Additions
- Niobium Alloys
- Nonmetals
- Physical Properties
- Rare Gases
- Reactor Materials
- Reactors
- Rene 80
- Rene-100
- Silicon Alloys
- Stresses
- Tantalum Alloys
- Titanium Alloys
- Tungsten Alloys
- Tungsten Base Alloys
- Zirconium Additions
- Zirconium Alloys 360103* -- Metals & Alloys-- Mechanical Properties
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- Report No.: COO-2975-43
- Grant Number: AC02-76ET34202
- Digital Object Identifier: https://doi.org/10.2172/5157795
- Office of Scientific & Technical Information Report Number: 5157795
- Archival Resource Key: ark:/67531/metadc1057563
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Office of Scientific & Technical Information Technical Reports
Reports, articles and other documents harvested from the Office of Scientific and Technical Information.
Office of Scientific and Technical Information (OSTI) is the Department of Energy (DOE) office that collects, preserves, and disseminates DOE-sponsored research and development (R&D) results that are the outcomes of R&D projects or other funded activities at DOE labs and facilities nationwide and grantees at universities and other institutions.
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Creation Date
- June 25, 1980
Added to The UNT Digital Library
- Jan. 22, 2018, 7:23 a.m.
Description Last Updated
- March 15, 2021, 5:17 p.m.
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Advanced Gas Cooled Nuclear Reactor Materials Evaluation and Development Program. Progress report, January 1, 1980-March 31, 1980, report, June 25, 1980; United States. (https://digital.library.unt.edu/ark:/67531/metadc1057563/: accessed June 2, 2024), University of North Texas Libraries, UNT Digital Library, https://digital.library.unt.edu; crediting UNT Libraries Government Documents Department.