Controlling cesium in the coolant of the Experimental Breeder Reactor II
Journal Article
·
· Nucl. Technol.; (United States)
OSTI ID:5646532
- Argonne National Lab., Idaho Falls, IA
Carbon has been shown to be an effective getter for cesium in liquid sodium. A cesium trap containing reticulated vitreous carbon and operating at 190/sup 0/C has been used at the Experimental Breeder Reactor II to reduce fission product cesium activity in the primary sodium coolant from a maximum of 15 kBq/g to approx. 870 Bq/g.
- OSTI ID:
- 5646532
- Journal Information:
- Nucl. Technol.; (United States), Journal Name: Nucl. Technol.; (United States) Vol. 46:2; ISSN NUTYB
- Country of Publication:
- United States
- Language:
- English
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21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
220600* -- Nuclear Reactor Technology-- Research
Test & Experimental Reactors
ALKALI METAL ISOTOPES
ALKALI METALS
BETA DECAY RADIOISOTOPES
BETA-MINUS DECAY RADIOISOTOPES
BREEDER REACTORS
CARBON
CESIUM 137
CESIUM ISOTOPES
COOLANT CLEANUP SYSTEMS
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EXPERIMENTAL REACTORS
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LMFBR TYPE REACTORS
METALS
NONMETALS
NUCLEI
ODD-EVEN NUCLEI
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PRIMARY COOLANT CIRCUITS
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REACTOR COMPONENTS
REACTOR COOLING SYSTEMS
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RESEARCH AND TEST REACTORS
SODIUM
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TESTING
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YEARS LIVING RADIOISOTOPES
220600* -- Nuclear Reactor Technology-- Research
Test & Experimental Reactors
ALKALI METAL ISOTOPES
ALKALI METALS
BETA DECAY RADIOISOTOPES
BETA-MINUS DECAY RADIOISOTOPES
BREEDER REACTORS
CARBON
CESIUM 137
CESIUM ISOTOPES
COOLANT CLEANUP SYSTEMS
COOLING SYSTEMS
EBR-2 REACTOR
ELEMENTS
EPITHERMAL REACTORS
EXPERIMENTAL REACTORS
FAST REACTORS
FBR TYPE REACTORS
ISOTOPES
LIQUID METAL COOLED REACTORS
LMFBR TYPE REACTORS
METALS
NONMETALS
NUCLEI
ODD-EVEN NUCLEI
PERFORMANCE TESTING
POWER REACTORS
PRIMARY COOLANT CIRCUITS
RADIOISOTOPES
REACTOR COMPONENTS
REACTOR COOLING SYSTEMS
REACTORS
RESEARCH AND TEST REACTORS
SODIUM
SODIUM COOLED REACTORS
TESTING
TRAPS
YEARS LIVING RADIOISOTOPES