FFTF operating experience with sodium natural circulation: slides included
Description
The Fast Flux Test Facility (FFTF) has been designed for passive, back-up, safety grade decay heat removal utilizing natural circulation of the sodium coolant. This paper discusses the process by which operator preparation for this emergency operating mode has been assured, in paralled with the design verification during the FFTF startup and acceptance testing program. Over the course of the test program, additional insights were gained through the testing program, through on-going plant analyses and through general safety evaluations performed throughout the nuclear industry. These insights led to development of improved operator training material for control of decay heat removal during both forced and natural circulation as well as improvements in the related plant operating procedures
Availability note (English)
MF available from INIS under the Report Number; Available from NTIS., PC A03/MF A01.Files
12638275.pdf
Files
(1.8 MB)
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Additional details
Publishing Information
- Imprint Pagination
- 33 p.
- Report number
- HEDL-SA--2326-FP
Conference
- Title
- American Nuclear Society's annual meeting.
- Dates
- 7 - 12 Jun 1981.
- Place
- Miami Beach, FL, USA.
INIS
- Country of Publication
- United States
- Country of Input or Organization
- United States
- INIS RN
- 12638275
- Subject category
- S61: RADIATION PROTECTION AND DOSIMETRY;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- AFTER-HEAT REMOVAL; EDUCATION; FFTF REACTOR; LOSS OF FLOW; NATURAL CONVECTION; REACTOR OPERATORS; REACTOR SAFETY; SAFETY ENGINEERING
- Descriptors DEC
- ACCIDENTS; CONVECTION; ENERGY TRANSFER; EPITHERMAL REACTORS; FAST REACTORS; HEAT TRANSFER; LIQUID METAL COOLED REACTORS; PERSONNEL; REACTOR ACCIDENTS; REACTORS; RESEARCH AND TEST REACTORS; RESEARCH REACTORS; SAFETY; SODIUM COOLED REACTORS; TEST REACTORS
Optional Information
- Secondary number(s)
- CONF-810606--88.