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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. 1980. "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 = 1980,
month = 3
}

Technical Report:

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  • Work covered includes an updated listing of the alloys selected for the screening tests, plus complete test specimen matrices for the screening program. The present design and construction status of the simulated reactor helium loops and testing and analysis facilities and equipment are discussed. Also covered are the loading matrices for the screening creep tests.
  • Work covered in this report includes the activities associated with the status of the simulated reactor helium supply systems and testing 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/sup 0/, 850/sup 0/, 950/sup 0/, and 1050/sup 0/C (1382/sup 0/, 1562/sup 0/, 1742/sup 0/, and 1922/sup 0/F). The status of controlled purity helium and air creep-rupture testing in the intensive screening test program is discussed. The results of metallographic studies of screening alloys exposed in controlled purity helium for 3000 hours at 750/supmore » 0/C and 6000 hours at 850/sup 0/C and for weldments exposed in controlled purity helium for 6000 hours at 850/sup 0/ and 950/sup 0/C are presented and discussed.« less
  • 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 qualificationmore » 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.« less
  • Results of work performed from July 1, 1978 through September 30, 1978 on the Advanced Gas Cooled Nuclear Reactor Materials Evaluation and Development Program are presented. Candidate alloys were evaluated for Very High Temperature Reactor Nuclear Process Heat (NPH) and Direct Cycle Helium Turbine (DCHT) applications, in terms of the affect of simulated reactor primary coolant (Helium containing small amounts of various other gases), the high temperatures, and long time exposures, on the mechanical properties and structural and surface stability of selected candidate alloys. The activities associated with the characterization of the materials for the screening test program are reported,more » i.e., test specimen preparation, information from the materials characterization tests performed by General Electric, and 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.« less
  • 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,more » 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.« less