Experiments of Self-wastage Phenomena Elucidation in Steam Generator Tube of Sodium-cooled Fast Reactor

作者：Ryota Umeda, K. Shimoyama, A. Kurihara · 发表于：Transactions of the Atomic Energy Society of Japan · 年份：2020 · DOI：10.3327/taesj.j19.012 · 研究领域：Materials Science

The sodium – water reaction caused by failure of the steam generator tube of sodium-cooled fast re-actors causes the wastage phenomenon, which is erosive and corrosive. Self-wastage takes place in the early stage of the sodium – water reaction event when a very small amount of water / steam penetrates a microcrack. When self-wastage proceeds to the inside wall of the tube, the failed area and water leakage rate will increase, whereby the area affected by the sodium – water reaction will be likely to ex-tend. Thus, it is very important to clarify the self-wastage behavior for a locally affected region and detect water leakage in actual nuclear power plants. In this study, the authors performed self-wastage experiments under a high sodium temperature condition to evaluate the effects of the wastage form / geometry using two types of initial defect, i.e., the microfine pinhole and fatigue crack, and of the water leakage rate on the self-wastage rate. Taking into consideration the influence of crack type, we confirmed that the self-wastage rate did not strongly depend on the initial defect geometry. As a mechanism of the self-plug phenomenon, it is speculated that sodium oxide blocks and inhibits the progress of self-wastage. The dependence of the self-wastage rate on the initial sodium temperature was clearly observed, and a new self-wastage correlation was derived considering the initial sodium temperature.