FAST FLUX TEST FACILITY (FFTF) A HISTORY OF SAFETY & OPERATIONAL EXCELLENCE.

FAST FLUX TEST FACILITY (FFTF) A HISTORY OF SAFETY & OPERATIONAL EXCELLENCE.
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Total Pages: 30
Release: 2004
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The Fast Flux Test Facility (FFTF) is a 400-megawatt (thermal) sodium-cooled, high temperature, fast neutron flux, loop-type test reactor. The facility was constructed to support development and testing of fuels, materials and equipment for the Liquid Metal Fast Breeder Reactor program. FFTF began operation in 1980 and over the next 10 years demonstrated its versatility to perform experiments and missions far beyond the original intent of its designers. The reactor had several distinctive features including its size, flux, core design, extensive instrumentation, and test features that enabled it to simultaneously carry out a significant array of missions while demonstrating its features that contributed to a high level of plant safety and availability. FFTF is currently being deactivated for final closure.

FFTF (Fast Flux Test Facility) Fuel Handling Experience (1979--1986).

FFTF (Fast Flux Test Facility) Fuel Handling Experience (1979--1986).
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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.

Fast Flux Test Facility

Fast Flux Test Facility
Author: United States. Congress. Senate. Committee on Energy and Natural Resources. Subcommittee on Energy Research and Development
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Total Pages: 48
Release: 1991
Genre: Government publications
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Fast Flux Test Facility Periodic Technical Report

Fast Flux Test Facility Periodic Technical Report
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Total Pages: 260
Release: 1969
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This report was prepared at Pacific Northwest Laboratory by Battelle-Northwest (BNW) under Contract No. AT(45-1)-1830 for the Atomic Energy Commission, Division of Reactor Development and Technology. It is a report on design-related technical progress for the Fast Flux Test Facility, during the period October 1, 1968 through February 28, 1969.

Fast Flux Test Facility

Fast Flux Test Facility
Author: United States. Congress. House. Committee on Science, Space, and Technology. Subcommittee on Energy Research and Development
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Total Pages: 138
Release: 1990
Genre: Material testing reactors
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Evaluation of the Status of the Fast Flux Test Facility Program

Evaluation of the Status of the Fast Flux Test Facility Program
Author: United States. General Accounting Office
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Total Pages: 38
Release: 1976
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The Fast Flux Test Facility (FFTF) was authorized by Congress in 1967. The FFTF is intended to test nuclear fuels and materials most apt to work safely and economically in future breeder reactors. The Energy Research and Development Agency believes that 37- and 19-pin tests will be adequate for closed loop test purposes; and 37-pin tests will provide valid and useful data for establishing design and operating limits. The construction project is now estimated to cost $540 million instead of the $87.5 million originally projected, and supporting costs are estimated at an additional $613 million. More than $200 million in breeder reactor program costs should also be recognized as FFTF costs. Since authorization, the project's completion date has been extended by more than 5 years to August 1978. Technical problems with major components of the heat transport system remain.