Advanced gas cooled nuclear reactor materials evaluation and development program. Progress report, July 1-September 30, 1983
This report presents the results of work performed from July 1, 1983 through September 30, 1983 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) applications, particularly nuclear process heat (NPH) applications, in terms of the effect of simulated reactor primary coolant (helium containing small amounts of various other gases), high temperatures, and long time exposure on the mechanical properties and structural and surface stability. A second objective is to select and recommend materials for future test facilities and more extensive qualification programs and to develop the critical high temperature materials data needed for the design of major system components, especially those in the primary coolant circuit. Work covered in this report includes the activities associated with modifications and operation of the simulated reactor helium supply system and testing equipment. Progress on the multispecimen creep testing extensions to 15,000 hours is discussed. The status of creep rupture testing in simulated HTGR helium and in air is covered. The status of fatigue testing in simulated HTGR helium is described; the test results obtained are listed and discussed. The status of materials and specimens procurement for the contract extension work is presented; also discussed is the status of exposures and testing for the contract extension work. 7 figures, 16 tables.
- Research Organization:
- General Electric Co., Schenectady, NY (USA). Advanced Reactor Systems Dept.
- DOE Contract Number:
- AC02-76ET34202
- OSTI ID:
- 5277798
- Report Number(s):
- DOE/ET/34202-90; ON: DE84006398
- Resource Relation:
- Other Information: Portions are illegible in microfiche products
- Country of Publication:
- United States
- Language:
- English
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Advanced-gas-cooled-nuclear-reactor materials evaluation and development program. Progress report, January 1, 1983-March 31, 1983
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Related Subjects
21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
CHROMIUM ALLOYS
CORROSION
CREEP
TENSILE PROPERTIES
YIELD STRENGTH
GCR TYPE REACTORS
MATERIALS TESTING
RESEARCH PROGRAMS
INCOLOY 800H
INCONEL 617
IRON BASE ALLOYS
NICKEL ALLOYS
NICKEL BASE ALLOYS
NIMONIC 86
STAINLESS STEEL-347
AIR
EXPERIMENTAL DATA
HELIUM
ALLOYS
ALUMINIUM ADDITIONS
ALUMINIUM ALLOYS
CARBON ADDITIONS
CHEMICAL REACTIONS
CHROMIUM STEELS
CHROMIUM-NICKEL STEELS
COBALT ALLOYS
CORROSION RESISTANT ALLOYS
DATA
ELEMENTS
FLUIDS
GAS COOLED REACTORS
GASES
GRAPHITE MODERATED REACTORS
HEAT RESISTANT MATERIALS
HEAT RESISTING ALLOYS
INCOLOY ALLOYS
INCONEL ALLOYS
INFORMATION
IRON ALLOYS
MANGANESE ADDITIONS
MANGANESE ALLOYS
MATERIALS
MECHANICAL PROPERTIES
MOLYBDENUM ALLOYS
NIMONIC
NIOBIUM ADDITIONS
NIOBIUM ALLOYS
NONMETALS
NUMERICAL DATA
RARE GASES
REACTORS
SILICON ADDITIONS
SILICON ALLOYS
STAINLESS STEELS
STEELS
TESTING
TITANIUM ADDITIONS
TITANIUM ALLOYS
360103* - Metals & Alloys- Mechanical Properties
210300 - Power Reactors
Nonbreeding
Graphite Moderated
360105 - Metals & Alloys- Corrosion & Erosion