Actions for FFTF and CRBRP intermediate heat exchanger design, testing, and fabrication
FFTF and CRBRP intermediate heat exchanger design, testing, and fabrication
- Author
- Devlin, R. W.
- Published
- United States : [publisher not identified], 1977.
[Oak Ridge, Tennessee] : [U.S. Atomic Energy Commission], 1977. - Physical Description
- microfiche : negative ; 11 x 15 cm
- Additional Creators
- Bresnahan, J. D.
- Summary
- The Heat Transport Systems of the Fast Flux Test Facility (FFTF) and the Clinch River Breeder Reactor Plant (CRBRP) include Intermediate Heat Exchangers (IHXs) to form barriers between the primary radioactive and secondary non-radioactive sodium coolant loops. The design, development and fabrication of the IHX for the FFTF has been completed and the units installed in the facility. The design and development of the IHX for the CRBRP has progressed through the performance sizing stage and flow testing of critical areas into early fabrication. The design evolution of these two heat exchangers may be considered a continuous development because the design and fabrication organizations have been the same for both units. Structural considerations to meet ASME Code requirements, support testing experience and manufacturing experience from the FFTF program have been factored into the CRBRP program. This paper outlines the similarities and differences between the FFTF and CRBRP designs. Special attention has been given to utilization of flow distribution devices and associated hydraulic testing, tube bundle and tube-to-tubesheet joint configurations, and fabrication differences.
- Report Numbers
- CONF-771217-2
- Other Subject(s)
- 21 specific nuclear reactors and associated plants
- 210500 - power reactors, breeding
- 220600 - nuclear reactor technology- research, test & experimental reactors
- Breeder reactors
- Clinch river breeder reactor
- Cooling systems
- Design
- Epithermal reactors
- Fabrication
- Fast reactors
- Fbr type reactors
- Fftf reactor
- Heat exchangers
- Liquid metal cooled reactors
- Power reactors
- Reactor components
- Reactor cooling systems
- Reactors
- Research and test reactors
- Research reactors
- Sodium cooled reactors
- Test reactors
- Testing
- Collection
- U.S. Atomic Energy Commission depository collection.
- Note
- DOE contract number: EY-76-C-02-3045-022
OSTI Identifier 5263338
Research organization: Westinghouse Electric Corp., Madison, PA (USA). Advanced Reactors Div.
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