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RANNS code analysis on the local mechanical conditions of cladding of high burnup fuel rods under PCMI in RIA-simulated experiments in NSRR

NSRRの反応度事故模擬実験における、高燃焼度燃料被覆管のPCMI状態での局所的な力学状況に関するRANNSによる解析

鈴木 元衛; 斎藤 裕明*; 更田 豊志

Suzuki, Motoe; Saito, Hiroaki*; Fuketa, Toyoshi

RANNSコードは反応度事故条件における燃料棒ふるまいを解析する。このコードは二種の力学モデルを持つ。一つは、燃料棒の各々の軸方向セグメント長における一次元変形モデルである。もう一つは、新開発の、一ペレット長における局所変形の二次元モデルである。NSRRにおける反応度事故を模擬した、高燃焼度PWR 燃料棒実験OI-10の解析を行い、被覆管変形について計算と実測で比較した。事故直前の燃料状態は燃料解析コードFEMAXI-6によって予測された。RANNSの二次元モデルの計算において、PCMIにおける被覆管のリッジ部の間の塑性歪み増加が計算と実測で比較検討され、局所的な不均一歪みに起因する応力の変動がクラック成長に与える影響を考察した。

The RANNS code analyzes behaviors of a single fuel rod in reactivity-initiated accident (RIA) conditions. The code has two types of mechanical model; one-dimensional deformation model for each axial segment length of rod, and newly-developed two-dimensional local deformation model for one pellet length. Analyses were performed on the RIA-simulated experiments in the Nuclear Safety Research Reactor (NSRR), OI-10, with high burnup PWR rods, and results of cladding deformation were compared between calculations by the two models and PIE data. The pre-accident, or End-of-Life conditions of the rods were predicted by the fuel performance code FEAMXI-6. In the calculations by the two-dimensional model of RANNS, the plastic strain increases at the cladding ridges during PCMI were compared with those in between the ridges and with the PIE data, and effect of stress variance induced by local non-uniformity of strain on the crack growth was discussed.

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パーセンタイル:52.47

分野:Nuclear Science & Technology

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