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JAEA studies on spent fuel pool severe accident, 1; Results of cladding air oxidation experiments

原子力機構における使用済み燃料プール事故に関する研究,1; 被覆管の空気中酸化挙動の評価

根本 義之; 小川 千尋; 加治 芳行; 中島 一雄*; 東條 匡志*; 後藤 大輔*

Nemoto, Yoshiyuki; Ogawa, Chihiro; Kaji, Yoshiyuki; Nakashima, Kazuo*; Tojo, Masayuki*; Goto, Daisuke*

使用済み燃料プール(SFP)水位低下時の事象解析を目的とした重大事故解析コードの高度化においては、高温の被覆管材料の空気中での酸化挙動のモデル化及びコードへの取り込みが必要である。そのためわれわれは、長尺の被覆管にSFP水位低下時を模擬した温度分布を与えた条件での酸化試験と、被覆管の小型サンプルの酸化試験を並行して実施し、その結果の比較から、酸化モデルの構築及び実炉のSFP条件への適用性検討を行うこととした。本報では、二つの酸化試験の結果及び今後の試験計画等について報告する。

To improve the severe accident codes for the analysis of spent fuel pool (SFP) accident with water level decrease, it is necessary to model the air oxidation behavior of the cladding based on experimental data. For the air oxidation modeling, it is necessary to understand the influence of temperature distribution along axial direction of the cladding in SFP accident condition. In addition, it is important to evaluate the influence of oxide film formed on surface of cladding during operation in nuclear power plant. In this study, bare specimens and pre-oxidized specimens of Japanese zircalloy-4 were investigated. Longer specimens of cladding were tested in air with temperature distribution along the axial direction of the cladding simulating the SFP accident condition. Shorter specimens were adopted for tests in thermogravimetry to obtain basic data. Experimental data were compared and the authors discussed on influence of the temperature distribution and oxide film for the air oxidation behavior.

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