Advanced Gas-Cooled Nuclear Reactor Materials Evaluation and Development Program. Progress report, April 1, 1979-June 30, 1979
The 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. Work covered in this report includes the activities associated with the status of the simulated reactor helium supply system, testing equipment, and gas chemistry analysis instrumentation and equipment. The status of the data management system is presented. In addition, the progress in the screening test program is described.
- Research Organization:
- General Electric Co., Schenectady, NY (USA). Energy Systems Programs Dept.
- DOE Contract Number:
- EY-76-C-02-2975
- OSTI ID:
- 5649241
- Report Number(s):
- COO-2975-34
- Country of Publication:
- United States
- Language:
- English
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INCONEL 617
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RENE 80
RENE-100
UDIMET ALLOYS
CREEP
DATA ACQUISITION
GAS TURBINES
STRESSES
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ALUMINIUM ALLOYS
BORON ADDITIONS
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CARBON ADDITIONS
CHROMIUM ALLOYS
CHROMIUM BASE ALLOYS
COBALT ALLOYS
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ELEMENTS
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GAS COOLED REACTORS
GRAPHITE MODERATED REACTORS
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INCONEL ALLOYS
IRON ALLOYS
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MACHINERY
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MOLYBDENUM ALLOYS
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NICKEL ALLOYS
NIOBIUM ADDITIONS
NIOBIUM ALLOYS
NONMETALS
RARE GASES
REACTORS
SILICON ALLOYS
TANTALUM ALLOYS
TITANIUM ALLOYS
TUNGSTEN ALLOYS
TUNGSTEN BASE ALLOYS
TURBINES
TURBOMACHINERY
ZIRCONIUM ADDITIONS
ZIRCONIUM ALLOYS
360103* - Metals & Alloys- Mechanical Properties
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