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Title: Advanced Gas-Cooled Nuclear Reactor Materials Evaluation and Development Program. Progress report, July 1, 1979-September 30, 1979

Abstract

The results of work performed from July 1, 1979 through September 30, 1979 on the Advanced Gas-Cooled Nuclear Reactor Materials Evaluation and Development Program are presented. 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.

Publication Date:
Research Org.:
General Electric Co., Schenectady, NY (USA). Energy Systems Programs Dept.
OSTI Identifier:
5669167
Report Number(s):
COO-2975-37
DOE Contract Number:
EY-76-C-02-2975
Resource Type:
Technical Report
Country of Publication:
United States
Language:
English
Subject:
36 MATERIALS SCIENCE; 21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS; ALLOY-HD-556; CORROSION RESISTANCE; ALLOY-IN-738; ALLOY-MO-RE-2; ALUMINIUM OXIDES; HASTELLOY X; HELIUM; CORROSIVE EFFECTS; HTGR TYPE REACTORS; REACTOR MATERIALS; INCONEL ALLOYS; MICROSTRUCTURE; MANAURITE 36X; NICHROME; RENE 80; CONTROLLED ATMOSPHERES; CREEP; EQUIPMENT; FATIGUE; GAS TURBINES; MATERIALS TESTING; RUPTURES; ALLOYS; ALUMINIUM ALLOYS; ALUMINIUM COMPOUNDS; ATMOSPHERES; BORON ADDITIONS; BORON ALLOYS; CARBON ADDITIONS; CHALCOGENIDES; CHROMIUM ALLOYS; CHROMIUM BASE ALLOYS; COBALT ALLOYS; CRYOGENIC FLUIDS; CRYSTAL STRUCTURE; ELEMENTS; FAILURES; FLUIDS; GAS COOLED REACTORS; GRAPHITE MODERATED REACTORS; HASTELLOYS; HEAT RESISTANT MATERIALS; HEAT RESISTING ALLOYS; IRON ALLOYS; MACHINERY; MANGANESE ALLOYS; MATERIALS; MECHANICAL PROPERTIES; MOLYBDENUM ALLOYS; NICKEL ALLOYS; NICKEL BASE ALLOYS; NIOBIUM ADDITIONS; NIOBIUM ALLOYS; NONMETALS; OXIDES; OXYGEN COMPOUNDS; RARE GASES; REACTORS; SILICON ALLOYS; TANTALUM ALLOYS; TESTING; TITANIUM ALLOYS; TUNGSTEN ALLOYS; TUNGSTEN BASE ALLOYS; TURBINES; TURBOMACHINERY; ZIRCONIUM ADDITIONS; ZIRCONIUM ALLOYS; 360103* - Metals & Alloys- Mechanical Properties; 360105 - Metals & Alloys- Corrosion & Erosion; 210300 - Power Reactors, Nonbreeding, Graphite Moderated; 360102 - Metals & Alloys- Structure & Phase Studies

Citation Formats

Not Available. Advanced Gas-Cooled Nuclear Reactor Materials Evaluation and Development Program. Progress report, July 1, 1979-September 30, 1979. United States: N. p., 1980. Web. doi:10.2172/5669167.
Not Available. Advanced Gas-Cooled Nuclear Reactor Materials Evaluation and Development Program. Progress report, July 1, 1979-September 30, 1979. United States. doi:10.2172/5669167.
Not Available. Fri . "Advanced Gas-Cooled Nuclear Reactor Materials Evaluation and Development Program. Progress report, July 1, 1979-September 30, 1979". United States. doi:10.2172/5669167. https://www.osti.gov/servlets/purl/5669167.
@article{osti_5669167,
title = {Advanced Gas-Cooled Nuclear Reactor Materials Evaluation and Development Program. Progress report, July 1, 1979-September 30, 1979},
author = {Not Available},
abstractNote = {The results of work performed from July 1, 1979 through September 30, 1979 on the Advanced Gas-Cooled Nuclear Reactor Materials Evaluation and Development Program are presented. 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.},
doi = {10.2172/5669167},
journal = {},
number = ,
volume = ,
place = {United States},
year = {Fri Mar 07 00:00:00 EST 1980},
month = {Fri Mar 07 00:00:00 EST 1980}
}

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