Advanced Gas Cooled Nuclear Reactor Materials Evaluation And Development Program
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Total Pages | : |
Release | : 1977 |
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Download Advanced Gas Cooled Nuclear Reactor Materials Evaluation and Development Program Book in PDF, Epub and Kindle
Results of work performed from January 1, 1977 through March 31, 1977 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) Process Heat and Direct Cycle Helium Turbine (DCHT) applications, in terms of the effect of simulated reactor primary coolant (impure Helium), 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 progress to date on alloy selection for VHTR Nuclear Process Heat (NPH) applications and for DCHT applications. The present status on the simulated reactor helium loop design and on designs for the testing and analysis facilities and equipment is discussed.
Author | : General Electric Company. Energy Systems Programs Department |
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Release | : 1978 |
Genre | : Cooling towers |
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Download Advanced gas cooled nuclear reactor materials evaluation and development program Book in PDF, Epub and Kindle
Author | : |
Publisher | : |
Total Pages | : |
Release | : 1979 |
Genre | : |
ISBN | : |
Download Advanced Gas Cooled Nuclear Reactor Materials Evaluation & Development Program Book in PDF, Epub and Kindle
Author | : General Electric Company. Energy Systems Programs Department |
Publisher | : |
Total Pages | : |
Release | : 1978 |
Genre | : Cooling towers |
ISBN | : |
Download Advanced gas cooled nuclear reactor materials evaluation and development program Book in PDF, Epub and Kindle
Author | : |
Publisher | : |
Total Pages | : |
Release | : 1980 |
Genre | : |
ISBN | : |
Download Advanced Gas Cooled Nuclear Reactor Materials Evaluation and Development, Program, Jan. 1, 1980-March 31, 1980 Book in PDF, Epub and Kindle
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Release | : 1981 |
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Download Advanced Gas Cooled Nuclear Reactor Materials Evaluation and Development Program. Progress Report for Period October 1, 1980-December 31, 1980 Book in PDF, Epub and Kindle
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Release | : 1978 |
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Download Advanced Gas Cooled Nuclear Reactor Materials Evaluation and Development Program. Selection of Candidate Alloys. Vol. 1. Advanced Gas Cooled Reactor Systems Definition Book in PDF, Epub and Kindle
Candidate alloys for a Very High Temperature Reactor (VHTR) Nuclear Process Heal (NPH) and Direct Cycle Helium Turbine (DCHT) applications in terms of the effect of the primary coolant exposure and thermal exposure were evaluated. (FS).
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Total Pages | : 74 |
Release | : 1982 |
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Download Advanced Gas-cooled Nuclear Reactor Materials Evaluation and Development Program : Corrosion Behaviour of Experimental Alloys in Controlled Purity Helium at Temperatures in the 750-1050 Deg. C Range Book in PDF, Epub and Kindle
Author | : |
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Total Pages | : |
Release | : 1977 |
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Download Advanced Gas Cooled Nuclear Reactor Materials Evaluation and Development Program. Progress Report, September 23, 1976--December 31, 1976 Book in PDF, Epub and Kindle
This report presents the results of work performed from September 23, 1976 through December 31, 1976 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) Process Heat and Direct Cycle Helium Turbine (DCHT) applications, in terms of the affect of simulated reactor primary coolant (impure Helium), 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 progress to date on alloy selection for VHTR Nuclear Process Heat (NPH) applications and for DCHT applications. The present status on the simulated reactor helium loop design and on designs for the testing and analysis facilities and equipment is discussed.
Author | : |
Publisher | : |
Total Pages | : |
Release | : 1980 |
Genre | : |
ISBN | : |
Download Advanced Gas Cooled Nuclear Reactor Materials Evaluation and Development Program. Progress Report, January 1, 1980-March 31, 1980 Book in PDF, Epub and Kindle
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°C.