OS8-4 サブチャンネル解析を用いた超臨界圧水冷却炉の炉心熱特性評価(OS8 軽水炉・新型炉・核燃料サイクル,分散と集中の共存)

概要

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Reactor core thermal characterization of supercritical water reactor (SCWR) was evaluated using subchannel analysis code SILFEED-SC. A conservative assumptions that the axial power peaking and the local power peaking were set to the severest values in the whole core were used for evaluations. The analyzed maximum fuel cladding surface temperature is 698℃ under the 6-division orifice conditions, and that temperature satisfies the limitation temperature of 700℃. It is clarified that the fuel cladding surface temperature rises greatly by the occurrence of the heat transfer deterioration due to a large axial power peaking at the beginning of the cycle and by the upper power peak at the end of the cycle. Therefore, the fuel cladding surface temperature is expected to be able to be decreased more if these power characterization was improved.
社団法人日本機械学会の論文
2006-06-28