Future Use Of The United States Department Of Energys Fast Flux Test Reactor PDF Download

Are you looking for read ebook online? Search for your book and save it on your Kindle device, PC, phones or tablets. Download Future Use Of The United States Department Of Energys Fast Flux Test Reactor PDF full book. Access full book title Future Use Of The United States Department Of Energys Fast Flux Test Reactor.

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
Publisher:
Total Pages: 138
Release: 1990
Genre: Material testing reactors
ISBN:

Download Fast Flux Test Facility Book in PDF, ePub and Kindle


Nuclear Science

Nuclear Science
Author: United States. General Accounting Office
Publisher:
Total Pages: 16
Release: 1992
Genre: Fast Flux Test Facility Program
ISBN:

Download Nuclear Science Book in PDF, ePub and Kindle


CLOSURE OF THE FAST FLUX TEST FACILITY (FFTF) CURRENT STATUS & FUTURE PLANS.

CLOSURE OF THE FAST FLUX TEST FACILITY (FFTF) CURRENT STATUS & FUTURE PLANS.
Author:
Publisher:
Total Pages:
Release: 2007
Genre:
ISBN:

Download CLOSURE OF THE FAST FLUX TEST FACILITY (FFTF) CURRENT STATUS & FUTURE PLANS. Book in PDF, ePub and Kindle

The Fast Flux Test Facility (FFTF) was a 400 MWt sodium-cooled fast reactor situated on the U.S. Department of Energy's (DOE) Hanford Site in the southeastern portion of Washington State. DOE issued the final order to shut down the facility in 2001, when it was concluded that there was no longer a need for FFTF. Deactivation activities are in progress to remove or stabilize major hazards and deactivate systems to achieve end points documented in the project baseline. The reactor has been defueled, and approximately 97% of the fuel has been removed from the facility. Approximately 97% of the sodium has been drained from the plant's systems and placed into an on-site Sodium Storage Facility. The residual sodium will be kept frozen under a blanket of inert gas until it is removed later as part of the facility's decontamination and decommissioning (D & D). Plant systems have been shut down and placed in a low-risk state to minimize requirements for surveillance and maintenance. D & D work cannot begin until an Environmental Impact Statement has been prepared to evaluate various end state options and to provide a basis for selecting one of the options. The Environmental Impact Statement is expected to be issued in 2009.


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
Publisher:
Total Pages: 38
Release: 1976
Genre:
ISBN:

Download Evaluation of the Status of the Fast Flux Test Facility Program Book in PDF, ePub and Kindle

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.


Five Years Operating Experience at the Fast Flux Test Facility

Five Years Operating Experience at the Fast Flux Test Facility
Author:
Publisher:
Total Pages:
Release: 1987
Genre:
ISBN:

Download Five Years Operating Experience at the Fast Flux Test Facility Book in PDF, ePub and Kindle

The Fast Flux Test Facility (FFTF) is a 400 Mw(t), loop-type, sodium-cooled, fast neutron reactor. It is operated by the Westinghouse Hanford Company for the United States Department of Energy at Richland, Washington. The FFTF is a multipurpose test reactor used to irradiate fuels and materials for programs such as Liquid Metal Reactor (LMR) research, fusion research, space power systems, isotope production and international research. FFTF is also used for testing concepts to be used in Advanced Reactors which will be designed to maximize passive safety features and not require complex shutdown systems to assure safe shutdown and heat removal. The FFTF also provides experience in the operation and maintenance of a reactor having prototypic components and systems typical of large LMR (LMFBR) power plants. The 5 year operational performance of the FFTF reactor is discussed in this report. 6 refs., 10 figs., 2 tabs.


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

FFTF (Fast Flux Test Facility) Fuel Handling Experience (1979--1986).
Author:
Publisher:
Total Pages:
Release: 1987
Genre:
ISBN:

Download FFTF (Fast Flux Test Facility) Fuel Handling Experience (1979--1986). Book in PDF, ePub and Kindle

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.


An Overview of FFTF (Fast Flux Test Facility) Contributions to Liquid Metal Reactor Safety

An Overview of FFTF (Fast Flux Test Facility) Contributions to Liquid Metal Reactor Safety
Author:
Publisher:
Total Pages: 8
Release: 1990
Genre:
ISBN:

Download An Overview of FFTF (Fast Flux Test Facility) Contributions to Liquid Metal Reactor Safety Book in PDF, ePub and Kindle

The Fast Flux Test Facility has provided a very useful framework for testing the advances in Liquid Metal Reactor Safety Technology. During the licensing phase, the switch from a nonmechanistic bounding technique to the mechanistic approach was developed and implemented. During the operational phase, the consideration of new tests and core configurations led to use of the anticipated-transients-without-scram approach for beyond design basis events and the move towards passive safety. The future role of the Fast Flux Test Facility may involve additional passive safety and waste transmutation tests. 26 refs.