Advanced Gas Cooled Nuclear Reactor Materials Evaluation and Development Program. Progress report, January 1, 1980-March 31, 1980
Abstract
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.
- Publication Date:
- Research Org.:
- General Electric Co., Schenectady, NY (USA). Energy Systems Programs Dept.
- OSTI Identifier:
- 5157795
- Report Number(s):
- COO-2975-43
- DOE Contract Number:
- AC02-76ET34202
- 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; CREEP; PHYSICAL PROPERTIES; ALLOY-HK-40; ALLOY-IN-519; ALLOY-IN-738; ALLOY-MM-0011; ALLOY-MO-RE-2; ALLOY-NX-188; ALLOY-TZM; HASTELLOY X; HELIUM; CORROSIVE EFFECTS; HTGR TYPE REACTORS; REACTOR MATERIALS; INCOLOY 800; INCOLOY 802; INCONEL 617; INCONEL 713LC; MANAURITE 36X; NICKEL BASE ALLOYS; RENE 80; RENE-100; MECHANICAL PROPERTIES; STRESSES; ALLOYS; ALUMINIUM ALLOYS; BORON ADDITIONS; BORON ALLOYS; CARBON ADDITIONS; CHROMIUM ALLOYS; CHROMIUM BASE ALLOYS; COBALT ALLOYS; CRYOGENIC FLUIDS; ELEMENTS; FLUIDS; GAS COOLED REACTORS; GRAPHITE MODERATED REACTORS; HASTELLOYS; HEAT RESISTANT MATERIALS; HEAT RESISTING ALLOYS; INCOLOY ALLOYS; INCONEL ALLOYS; IRON ALLOYS; IRON BASE ALLOYS; MANGANESE ALLOYS; MATERIALS; MOLYBDENUM ALLOYS; MOLYBDENUM BASE ALLOYS; NICKEL ALLOYS; NIOBIUM ADDITIONS; NIOBIUM ALLOYS; NONMETALS; RARE GASES; REACTORS; SILICON ALLOYS; TANTALUM ALLOYS; TITANIUM ALLOYS; TUNGSTEN ALLOYS; TUNGSTEN BASE ALLOYS; ZIRCONIUM ADDITIONS; ZIRCONIUM ALLOYS; 360103* - Metals & Alloys- Mechanical Properties; 360104 - Metals & Alloys- Physical Properties; 360105 - Metals & Alloys- Corrosion & Erosion; 210300 - Power Reactors, Nonbreeding, Graphite Moderated
Citation Formats
. Advanced Gas Cooled Nuclear Reactor Materials Evaluation and Development Program. Progress report, January 1, 1980-March 31, 1980. United States: N. p., 1980.
Web. doi:10.2172/5157795.
. Advanced Gas Cooled Nuclear Reactor Materials Evaluation and Development Program. Progress report, January 1, 1980-March 31, 1980. United States. https://doi.org/10.2172/5157795
. 1980.
"Advanced Gas Cooled Nuclear Reactor Materials Evaluation and Development Program. Progress report, January 1, 1980-March 31, 1980". United States. https://doi.org/10.2172/5157795. https://www.osti.gov/servlets/purl/5157795.
@article{osti_5157795,
title = {Advanced Gas Cooled Nuclear Reactor Materials Evaluation and Development Program. Progress report, January 1, 1980-March 31, 1980},
author = {},
abstractNote = {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.},
doi = {10.2172/5157795},
url = {https://www.osti.gov/biblio/5157795},
journal = {},
number = ,
volume = ,
place = {United States},
year = {Wed Jun 25 00:00:00 EDT 1980},
month = {Wed Jun 25 00:00:00 EDT 1980}
}