Operational safety at the FFTF
Conference
·
OSTI ID:5598699
An extensive operational nuclear safety program has been an integral part of the design, startup, and initial operating phases of the Fast Flux Test Facility (FFTF). During the design and construction of the facility, a program of independent safety overviews and analyses assured the provision of responsible safety margins within the plant, protective systems, and engineered safety features for protection of the public, operating staff, and the facility. The program is continuing through surveillance of operations to verify continued adherence to the established operating envelope and for timely identification of any trends potentially adverse to those margins. Experience from operation of FFTF is being utilized in the development of enhanced operational nuclear safety aids for application in follow-on breeder reactor power systems. The commendable plant and personnel safety experiences of FFTF through its startup and ascension to full power demonstrate the overall effectiveness of the FFTF operational nuclear safety program.
- Research Organization:
- Hanford Engineering Development Lab., Richland, WA (USA)
- DOE Contract Number:
- AC06-76FF02170
- OSTI ID:
- 5598699
- Report Number(s):
- HEDL-SA-2304; CONF-811008-4; ON: DE82003794
- Country of Publication:
- United States
- Language:
- English
Similar Records
Operational safety at the FFTF
Safety related experience in FFTF startup and operation
FFTF operational results
Journal Article
·
Thu Oct 01 00:00:00 EDT 1981
· Am. Soc. Mech. Eng., (Pap.); (United States)
·
OSTI ID:5686018
Safety related experience in FFTF startup and operation
Conference
·
Tue Jun 01 00:00:00 EDT 1982
·
OSTI ID:5047929
FFTF operational results
Conference
·
Thu Jul 01 00:00:00 EDT 1982
·
OSTI ID:6627472
Related Subjects
21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
22 GENERAL STUDIES OF NUCLEAR REACTORS
220600 -- Nuclear Reactor Technology-- Research
Test & Experimental Reactors
220900* -- Nuclear Reactor Technology-- Reactor Safety
ENGINEERED SAFETY SYSTEMS
EPITHERMAL REACTORS
FAST REACTORS
FFTF REACTOR
INJURIES
LIQUID METAL COOLED REACTORS
OPERATION
PERSONNEL
REACTOR OPERATION
REACTOR PROTECTION SYSTEMS
REACTOR SAFETY
REACTORS
RESEARCH AND TEST REACTORS
RESEARCH REACTORS
SAFETY
SODIUM COOLED REACTORS
TEST REACTORS
22 GENERAL STUDIES OF NUCLEAR REACTORS
220600 -- Nuclear Reactor Technology-- Research
Test & Experimental Reactors
220900* -- Nuclear Reactor Technology-- Reactor Safety
ENGINEERED SAFETY SYSTEMS
EPITHERMAL REACTORS
FAST REACTORS
FFTF REACTOR
INJURIES
LIQUID METAL COOLED REACTORS
OPERATION
PERSONNEL
REACTOR OPERATION
REACTOR PROTECTION SYSTEMS
REACTOR SAFETY
REACTORS
RESEARCH AND TEST REACTORS
RESEARCH REACTORS
SAFETY
SODIUM COOLED REACTORS
TEST REACTORS