Actions for Fast Flux Test Facility Reference Concept (Progress Report).
Fast Flux Test Facility Reference Concept (Progress Report).
- Author
- Boyd, C. L.
- Published
- United States : [publisher not identified], 1967.
[Oak Ridge, Tennessee] : [U.S. Atomic Energy Commission], 1967. - Physical Description
- microfiche : negative ; 11 x 15 cm
- Additional Creators
- Shadel, F. H. and Westsik, J. H.
- Summary
- The concept of the Fast Fuels Test Facility described In this document was developed to fulfill the objectives of: (1) Providing an adequately controlled environment in fast neutron flux for highly instrumented fuels and materials irradiation tests with capabilities for fuels testing to failure in dynamic sodium and for testing specimens for short duration (minutes); (2) Providing facilities for preirradiation testing to characterize the experiments for safety and performance, for interim nondestructive examination and for postirradiation examination; (3) Serving all U.S. fast flux needs consistent with the primary objective of fuels and materials testing. This progress report was prepared to describe the current FFTF concept based upon the results of the agreements with the AEC on the major conceptual features, and the status of the continuing conceptual design effort.
- Report Numbers
- BNWL-470
- Other Subject(s)
- 21 specific nuclear reactors and associated plants
- 42 engineering
- Air
- Computers
- Concept
- Containment
- Control systems
- Criticality
- Design
- Diagrams
- Digital systems
- Electricity
- Examination
- Fast flux
- Fftf
- Ftr
- Fuel elements
- Fuel handling
- Fuel
- Gas flow
- Heat exchangers
- Heat transfer
- Helium
- Impurities
- Inert gas
- Instruments
- Irradiation
- Liquid metal coolant
- Liquids
- Mass
- N38500 -research & test reactors & critical assemblies
- Nuclear criticality safety program (ncsp).
- Nuclear proof test facility
- Numericals
- Openings
- Operation
- Performance data
- Performance
- Physics
- Pipes
- Plutonium 239
- Pnnl
- Progress report
- Rabbits
- Reactor core
- Reactor
- Reflectors
- Research reactors
- Safety
- Service
- Shielding
- Sodium
- Structure
- Subassembly
- Testing
- Transport
- Utilities
- Waste disposal
- Collection
- U.S. Atomic Energy Commission depository collection.
- Note
- DOE contract number: AT(45-1)-1830
NSA number: NSA-22-014250
OSTI Identifier 4559620
Research organization: Battelle Pacific Northwest Labs., Richland, WA (United States). - Funding Information
- Sponsored by US Atomic Energy Commission (AEC).
Sponsored by USDOE National Nuclear Security Administration (NNSA), Nuclear Criticality Safety Program (NCSP).
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