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Problems in liquid sodium corrosion (in Japanese)

Journal Article · · Zairyo Kagaku, v. 9, no. 3, pp. 141-149
OSTI ID:4386502
Fundamental studies on the corrosion of metal, particularly stainless steel, by liquid sodium are reviewed. Temperaturegradient mass-transfer phenomena are stressed. The phenomena are influenced by local tempernture, temperature difference, temperature distribution over whole loop, flow speed, concentration of nonmetallic impurity, and usage history of the loop. Further, erosion, biting and self-bonding, as well as corrosion of bare metal without protective layer, should be taken into consideration. Solubility of iron, chromium, and nickel in the liquid sodium is sufficiently low so that these metals can be employed in practice. Solubility diagrams for metal, oxygen; and hydrogen in the liquid sodium, and free-energy diagrams for oxide formation and carbide formation are shown. Most carbides can be used as construction material to contain the liquid sodium. Advancement of liquidsodium technology depends upon usability of stainless steel. An experiment on mass transfer of pure metal such as iron, nickel, chromium, and cobalt in a thermal-convection loop made of 316 SS, is reviewed. In actual nuclear reactors, transfer of metal activated in the reactor core becomes a problem, because the lifetime of cold traps is restricted; deposited induced radioactivity makes both maintenance and replacement difficult, rather than blockage with oxide. The hot steel test loop project has been restored at Oarai. Corrosion of Ni, V, Nb, Mo, graphite-- C, UO/ sub 2/, UC, etc. are summarized briefly. (JA)
Research Organization:
Japan Atomic Energy Research Inst., Tokai
NSA Number:
NSA-29-016211
OSTI ID:
4386502
Journal Information:
Zairyo Kagaku, v. 9, no. 3, pp. 141-149, Journal Name: Zairyo Kagaku, v. 9, no. 3, pp. 141-149; ISSN ZAKGA
Country of Publication:
Japan
Language:
Japanese