Thermomigration of tritium in V-4Cr-4Ti alloy

• Published in: Journal of nuclear materials Vol. 417; no. 1-3; pp. 1175 - 1178
• Main Authors: Hashizume, Kenichi, Ogushi, Kazuhiro, Otsuka, Teppei, Tanabe, Tetsuo
• Format: Journal Article Conference Proceeding
• Language: English
• Published: Amsterdam Elsevier B.V 01.10.2011; Elsevier
• Subjects: Applied sciences; Controled nuclear fusion plants; Energy; Energy. Thermal use of fuels; Exact sciences and technology; Fission nuclear power plants; Fuels; Installations for energy generation and conversion: thermal and electrical energy; Nuclear fuels; Nuclear fusion reactor; Blanket; Cooling; Hydrogen; Concentration effect; Tritium; Temperature gradient; First wall; Nuclear reactor
• ISSN: 0022-3115; 1873-4820
• DOI: 10.1016/j.jnucmat.2010.12.074

In order to obtain heat of transport, Q∗, of tritium in V-4Cr-4Ti alloy (NIFS-HEAT-2), thermomigration experiments have been carried out at a temperature ranging from 333 to 471K. Tritium homogeneously distributed in the specimen bar was forced to migrate by an applied temperature gradient. The resulting tritium profile was visualized by an imaging plate technique and Q∗ was determined from the profile according to a thermomigration theory. The obtained value of Q∗ was about +20kJ/mol for the initial hydrogen concentration of 0.008at.%, and no appreciable temperature dependence was observed. In order to examine the effect of thermomigration on tritium retentions in pure V and the alloy used as cooling tubes or first walls of the blanket, a simple model calculation was made under designed temperature gradients in fusion reactors. The result showed that tritium retention could be enhanced about 10–20% compared with the case without thermomigration.