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Use of zirconium in liquid‐sodium systems
Author(s) -
Bowman F. E.,
Cubicciotti D. D.
Publication year - 1956
Publication title -
aiche journal
Language(s) - English
Resource type - Journals
SCImago Journal Rank - 0.958
H-Index - 167
eISSN - 1547-5905
pISSN - 0001-1541
DOI - 10.1002/aic.690020209
Subject(s) - zirconium , sodium , sodium cooled fast reactor , impurity , hydrogen , zirconium alloy , oxygen , materials science , nitrogen , chemistry , inorganic chemistry , metallurgy , nuclear chemistry , organic chemistry
Abstract The attractive nuclear properties of zirconium make it a highly desirable core material for sodium‐cooled reactors. The elevated temperature strength while low is sufficient for certain applications. Development of higher strength alloys is underway. Sodium in itself is completely compatible with zirconium; however, the nonmetallic contaminants, namely oxygen, hydrogen, and nitrogen, can effect serious damage. The primary problem in the use of zirconium in a sodium system, then, lies in controlling these impurities in the sodium.