FFTF (Fast Flux Test Facility) cesium trap design, installation, and operating experience
Conference
·
OSTI ID:6870079
The Fast Flux Test Facility (FFTF) is a 400-MWt, sodium-cooled reactor located on the Hanford Site near Richland, Washington, USA. The FFTF is owned by the U.S. Department of Energy and is operated by the Westinghouse Hanford Company. The FFTF was designed to test fuels and materials for use in liquid metal reactors. Since initial operation in 1982, anticipated breaches of experimental fuel pins have released fission products, including cesium, into the primary sodium. Because of its high volatility, cesium vaporizes into the cover gas space, where it condenses on components and equipment and is transported into the cover gas outlet. Because of the long half-life of /sup 137/Cs, these deposits result in long-term, local radiation levels that make contact maintenance difficult. Thus, a cesium trap was installed in FFTF to reduce the cesium level in the sodium. The trap could also permit a Run Beyond Cladding Breach (RBCB) program without compromising the sodium purity. Approximately 12 years of operating experience with a cesium trap at the Experimental Breeder Reactor II (EBR-II), located at Idaho Falls, Idaho provided the design basis for the FFTF cesium trap. 2 refs., 8 figs., 3 tabs.
- Research Organization:
- Westinghouse Hanford Co., Richland, WA (USA)
- DOE Contract Number:
- AC06-87RL10930
- OSTI ID:
- 6870079
- Report Number(s):
- WHC-SA-0134; CONF-881009-2; ON: DE88013670
- Country of Publication:
- United States
- Language:
- English
Similar Records
Liquid metal reactor cover gas purification and analysis in the USA
Operational safety experience and passive safety testing at the FFTF
Startup of the FFTF sodium cooled reactor
Conference
·
Mon Sep 01 00:00:00 EDT 1986
·
OSTI ID:6993685
Operational safety experience and passive safety testing at the FFTF
Conference
·
Mon Feb 29 23:00:00 EST 1988
·
OSTI ID:6779484
Startup of the FFTF sodium cooled reactor
Conference
·
Sat Aug 01 00:00:00 EDT 1981
· Proc., Intersoc. Energy Convers. Eng. Conf.; (United States)
·
OSTI ID:5238055
Related Subjects
21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
210500* -- Power Reactors
Breeding
ALKALI METAL ISOTOPES
ALKALI METALS
BETA DECAY RADIOISOTOPES
BETA-MINUS DECAY RADIOISOTOPES
CESIUM 137
CESIUM ISOTOPES
DATA
DESIGN
DIAGRAMS
ELEMENTS
ENERGY SOURCES
ENERGY TRANSFER
EPITHERMAL REACTORS
FAST REACTORS
FFTF REACTOR
FLOWSHEETS
FLUID FLOW
FLUID MECHANICS
FUEL ELEMENTS
FUEL PINS
FUELS
HEAT TRANSFER
HYDRAULICS
INFORMATION
ISOTOPES
LIQUID METAL COOLED REACTORS
MATERIALS
MECHANICS
METALS
NUCLEAR FUELS
NUCLEI
NUMERICAL DATA
ODD-EVEN NUCLEI
RADIATION PROTECTION
RADIOISOTOPES
REACTOR COMPONENTS
REACTOR MATERIALS
REACTOR SAFETY
REACTORS
REMOVAL
RESEARCH AND TEST REACTORS
RESEARCH REACTORS
SAFETY
SODIUM
SODIUM COOLED REACTORS
TEST REACTORS
YEARS LIVING RADIOISOTOPES
210500* -- Power Reactors
Breeding
ALKALI METAL ISOTOPES
ALKALI METALS
BETA DECAY RADIOISOTOPES
BETA-MINUS DECAY RADIOISOTOPES
CESIUM 137
CESIUM ISOTOPES
DATA
DESIGN
DIAGRAMS
ELEMENTS
ENERGY SOURCES
ENERGY TRANSFER
EPITHERMAL REACTORS
FAST REACTORS
FFTF REACTOR
FLOWSHEETS
FLUID FLOW
FLUID MECHANICS
FUEL ELEMENTS
FUEL PINS
FUELS
HEAT TRANSFER
HYDRAULICS
INFORMATION
ISOTOPES
LIQUID METAL COOLED REACTORS
MATERIALS
MECHANICS
METALS
NUCLEAR FUELS
NUCLEI
NUMERICAL DATA
ODD-EVEN NUCLEI
RADIATION PROTECTION
RADIOISOTOPES
REACTOR COMPONENTS
REACTOR MATERIALS
REACTOR SAFETY
REACTORS
REMOVAL
RESEARCH AND TEST REACTORS
RESEARCH REACTORS
SAFETY
SODIUM
SODIUM COOLED REACTORS
TEST REACTORS
YEARS LIVING RADIOISOTOPES