FFTF operating experience with sodium natural circulation: slides included
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.
- Research Organization:
- Hanford Engineering Development Lab., Richland, WA (USA)
- DOE Contract Number:
- AC14-76FF02170
- OSTI ID:
- 6204408
- Report Number(s):
- HEDL-SA-2326-FP; CONF-810606-88; ON: DE81027846; TRN: 81-015154
- Resource Relation:
- Conference: American Nuclear Society's annual meeting, Miami Beach, FL, USA, 7 Jun 1981
- Country of Publication:
- United States
- Language:
- English
Similar Records
Operational safety experience and passive safety testing at the FFTF
Natural circulation in FFTF
Related Subjects
21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
FFTF REACTOR
REACTOR OPERATORS
RHR SYSTEMS
AFTER-HEAT REMOVAL
EDUCATION
ENGINEERED SAFETY SYSTEMS
LOSS OF FLOW
NATURAL CONVECTION
REACTOR SAFETY
ACCIDENTS
CONVECTION
COOLING SYSTEMS
ENERGY SYSTEMS
EPITHERMAL REACTORS
FAST REACTORS
LIQUID METAL COOLED REACTORS
PERSONNEL
REACTOR ACCIDENTS
REACTOR COMPONENTS
REACTOR COOLING SYSTEMS
REACTORS
REMOVAL
RESEARCH AND TEST REACTORS
RESEARCH REACTORS
SAFETY
SODIUM COOLED REACTORS
TEST REACTORS
220900* - Nuclear Reactor Technology- Reactor Safety
220600 - Nuclear Reactor Technology- Research
Test & Experimental Reactors