Advanced Gas Cooled Nuclear Reactor Materials Evaluation and Development Program. Progress report, July 1, 1980-September 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: screening creep results and metallographic analysis for materials thermally exposed or tested at 750, 850, 950 and 1050/sup 0/C. Initiation of controlled purity helium creep-rupture testing in the intensive screening test program is discussed. In addition, the results of 1000-hour exposures at 750 and 850/sup 0/C on several experimental alloys are discussed.
- Research Organization:
- General Electric Co., Schenectady, NY (USA). Energy Systems Programs Dept.
- DOE Contract Number:
- AC02-76ET34202
- OSTI ID:
- 7079888
- Report Number(s):
- DOE/ET/34202-48; TRN: 81-002554
- Country of Publication:
- United States
- Language:
- English
Similar Records
Advanced Gas Cooled Nuclear Reactor Materials Evaluation and Development Program. Progress report, January 1, 1980-March 31, 1980
Advanced Gas Cooled Nuclear Reactor Materials Evaluation and Development Program. Progress report, January 1, 1981-March 31, 1981
Related Subjects
HELIUM COOLED REACTORS
REACTOR MATERIALS
HTGR TYPE REACTORS
PROCESS HEAT REACTORS
PERFORMANCE TESTING
VHTR REACTOR
CORROSION RESISTANCE
CREEP
DIRECT CYCLE COOLING SYSTEMS
MECHANICAL PROPERTIES
RESEARCH PROGRAMS
RUPTURES
VERY HIGH TEMPERATURE
COOLING SYSTEMS
ENRICHED URANIUM REACTORS
EXPERIMENTAL REACTORS
FAILURES
GAS COOLED REACTORS
GRAPHITE MODERATED REACTORS
MATERIALS
POWER REACTORS
REACTOR COMPONENTS
REACTOR COOLING SYSTEMS
REACTORS
RESEARCH AND TEST REACTORS
TESTING
THERMAL REACTORS
210300* - Power Reactors
Nonbreeding
Graphite Moderated
210900 - Nuclear Power Plants- Process Heat Reactors- (-1987)