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Controlling cesium in the coolant of the Experimental Breeder Reactor II

Journal Article · · Nucl. Technol.; (United States)
OSTI ID:5646532
 [1];
  1. 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