Advanced Gas Cooled Nuclear Reactor Materials Evaluation and Development Program. Progress report, April 1, 1980-June 30, 1980
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 progress in the screening test program is described; this includes: screening creep results and metallographic analysis for materials thermally exposed or tested at 750, 850 and 950/sup 0/C. The initiation of air creep-rupture testing in the intensive screening test program is discussed. In addition, the status of the data management system is described.
- Publication Date:
- OSTI Identifier:
- Report Number(s):
- DOE Contract Number:
- Resource Type:
- Technical Report
- Research Org:
- General Electric Co., Schenectady, NY (USA). Energy Systems Programs Dept.
- Country of Publication:
- United States
- 21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS; HTGR TYPE REACTORS; REACTOR MATERIALS; PROCESS HEAT REACTORS; ALLOYS; HELIUM COOLED REACTORS; MECHANICAL PROPERTIES; RESEARCH PROGRAMS; SIMULATION; STABILITY; GAS COOLED REACTORS; GRAPHITE MODERATED REACTORS; MATERIALS; REACTORS 210300* -- Power Reactors, Nonbreeding, Graphite Moderated; 210900 -- Nuclear Power Plants-- Process Heat Reactors-- (-1987)
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