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Title: 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

Not Available. 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.
Not Available. Advanced Gas Cooled Nuclear Reactor Materials Evaluation and Development Program. Progress report, January 1, 1980-March 31, 1980. United States. doi:10.2172/5157795.
Not Available. 1980. "Advanced Gas Cooled Nuclear Reactor Materials Evaluation and Development Program. Progress report, January 1, 1980-March 31, 1980". United States. doi: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 = {Not Available},
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},
journal = {},
number = ,
volume = ,
place = {United States},
year = 1980,
month = 6
}

Technical Report:

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  • This report presents the results of work performed from January 1, 1982 through March 31, 1982 on the Advanced Gas-Cooled Nuclear Reactor Materials Evaluation and Development Program. 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 analyses 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) in controlled-purity helium. The status of creep-rupture in controlled-puritymore » helium and air and fatigue testing in controlled-purity helium and air in the intensive screening test program is discussed. The results of metallographic studies of multispecimen creep specimens tested at 950/sup 0/C for 6000 hours (solid solution strengthened alloys and an iron-base oxide dispersion strengthened alloy) are presented and discussed.« less
  • The activities associated with the procurement of the materials for the screening test program, information from vendor certification for the materials received, and preliminary information from the materials characterization tests performed by GE are reported. The construction status of the simulated reactor helium supply system, testing equipment, and gas chemistry analysis instrumentation and equipment are discussed. The final recommended impurity levels for the screening phase helium are presented and the rational behind this gas chemistry is discussed. The status of the data management system is presented.
  • This report presents the results of work performed from January 1, 1983 through March 31, 1983 on the Advanced Gas-Cooled Nuclear Reactor Materials Evaluation and Development Program. 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 materialsmore » procurement for the contract extension work is presented.« less
  • Objectives 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 exposures on the mechanical properties and structural and surface stability. Work covered in this report includes the activities associated with the status of the simulated reactor helium supply systems and testing equipment. 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, 950,more » and 1050/sup 0/C. Status of controlled purity helium and air creep-rupture testing in the intensive screening test program is discussed. Results of metallographic studies of screening alloys exposed in controlled purity helium from 1000 hours at 1050/sup 0/C and 3000 hours at 850/sup 0/C are presented.« less
  • This report presents the results of work performed from January 1, 1979 through March 31, 1979 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. Work covered in this report includes the activitiesmore » associated with the creep-rupture testing of the test materials for the purpose of verifying the stresses selected for the screening creep test program, and the status of the simulated reactor helium supply system, testing equipment, and gas chemistry analysis instrumentation and equipment.« less