Fast Flux Test Facility Fuel Handling System Group 40 Fuel Handling And Radioactive Maintenance Objectives Requirements And Criteria
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Total Pages | : 28 |
Release | : 1966 |
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This report discusses the objectives of the FFTF Fuel Handling and Radioactive Maintenance System Group which are: To remove and replace test components from the reactor core under a controlled environment to permit maximum acquisition and preservation of experimental data; to service and maintain the reactor core to enable maximum utilization of the irradiation capability of the facility; and to provide the radioactive maintenance capability consistent with the requirement for high plant factor and safety considerations.
Author | : H. D. Lenkerskorfer |
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Total Pages | : 0 |
Release | : 1966 |
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Total Pages | : 578 |
Release | : 1993-10 |
Genre | : Power resources |
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Total Pages | : 1166 |
Release | : 1975 |
Genre | : Nuclear energy |
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Total Pages | : |
Release | : 1987 |
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The Fast Flux Test Facility (FFTF)is a 400 MW (th) sodium-cooled fast flux test reactor located on the Hanford Site in southeastern Washington State. The FFTF is operated by the Westinghouse Hanford Company for the United States Department of Energy. The FFTF is a three loop plant designed primarily for the purpose of testing full-scale core components in an environment prototypic of future liquid metal reactors. The plant design emphasizes features to enhance this test capability, especially in the area of the core, reactor vessel, and refueling system. Eight special test positions are provided in the vessel head to permit contact instrumented experiments to be installed and irradiated. These test positions effectively divide the core into three sectors. Each sector requires its own In-Vessel Handling Machine (IVHM) to access all the core positions. Since the core and the in-vessel refueling components are submerged under sodium, all handling operations must be performed blind. This puts severe requirements on the positioning ability are reliability of the refueling components. This report addresses the operating experience with the fuel handling system from initial core loading in November, 1979 through 1986. This includes 9 refueling cycles. 2 refs., 8 figs.
Author | : |
Publisher | : DIANE Publishing |
Total Pages | : 176 |
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ISBN | : 1428918345 |
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Total Pages | : 24 |
Release | : 1993 |
Genre | : Nuclear power plants |
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Author | : Fast Flux Test Facility (Wash.) |
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Total Pages | : |
Release | : 1975 |
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Total Pages | : 206 |
Release | : 1993 |
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This report provides Final Safety Analysis Report (FSAR) Amendment 73 for incorporation into the Fast Flux Test Facility (FFTR) FSAR set. This page change incorporates Engineering Change Notices (ECNs) issued subsequent to Amendment 72 and approved for incorparoration before May 6, 1993. These changes include: Chapter 3, design criteria structures, equipment, and systems; chapter 5B, reactor coolant system; chapter 7, instrumentation and control systems; chapter 9, auxiliary systems; chapter 11, reactor refueling system; chapter 12, radiation protection and waste management; chapter 13, conduct of operations; chapter 17, technical specifications; chapter 20, FFTF criticality specifications; appendix C, local fuel failure events; and appendix Fl, operation at 680°F inlet temperature.
Author | : United States. Congress. House. Committee on Science. Subcommittee on Energy and Environment |
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Total Pages | : 2172 |
Release | : 2001 |
Genre | : Energy development |
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