Model calculation of Cr dissolution behavior of ODS ferritic steel in high-temperature flowing sodium environment

JOURNAL OF NUCLEAR MATERIALS

卷:505

Article

Ohtsuka, Satoshi¹  Tanno, Takashi¹  Oka, Hiroshi¹  Yano, Yasuhide¹  Kato, Shoichi¹  Furukawa, Tomohiro¹  Kaito, Takeji¹ 

[1] Japan Atom Energy Agcy, 4002 Narita Cho, Oarai, Ibaraki 3111393, Japan

关键词: Oxide dispersion strengthened steel;    Fuel cladding tube;    Sodium-cooled fast reactor;    Cr dissolution;    Flowing sodium;   

DOI  :  10.1016/j.jnucmat.2018.03.054

来源: Elsevier

【 摘 要 】

A calculation model was constructed to systematically study the effects of environmental conditions (i.e. Cr concentration in sodium, test temperature, axial temperature gradient of fuel pin, and sodium flow velocity) on Cr dissolution behavior. Chromium dissolution was largely influenced by small changes in Cr concentration (i.e. chemical potential of Cr) in liquid sodium in the model calculation. Chromium concentration in sodium coolant, therefore, should be recognized as a critical parameter for the prediction and management of Cr dissolution behavior in the sodium-cooled fast reactor (SFR) core. Because the fuel column length showed no impact on dissolution behavior in the model calculation, no significant downstream effects possibly take place in the SFR fuel cladding tube due to the much shorter length compared with sodium loops in the SFR plant and the large axial temperature gradient. The calculated profile of Cr concentration along the wall-thickness direction was consistent with that measured in BOR-60 irradiation test where Cr concentration in inlet sodium bulk flow was set at 0.07 wt ppm in the calculation. (C) 2018 Elsevier B.V. All rights reserved.

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