反応度事故条件下における照射済BWR燃料の挙動; FK-1, -2 及び -3実験結果

Material type: 文書・図像類

Author: 杉山智之ほか

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Publication date: 2004-01

Material Format: Digital

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Note (General)：: Boiling water reactor (BWR) fuels with burnups of 41 to 45 GWd/tU were pulse-irradiated in the Nuclear Safety Research Reactor (NSRR) to investigate f...

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Summary, etc.：: Boiling water reactor (BWR) fuels with burnups of 41 to 45 GWd/tU were pulse-irradiated in the Nuclear Safety Research Reactor (NSRR) to investigate f...

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Material Type: 文書・図像類
Title: 反応度事故条件下における照射済BWR燃料の挙動; FK-1, -2 及び -3実験結果
Author/Editor: 杉山智之
中村武彦
草ヶ谷和幸
笹島栄夫
永瀬文久
更田豊志
Author Heading: 杉山智之
中村武彦
草ヶ谷和幸
笹島栄夫
永瀬文久
更田豊志
Publication Date: 2004-01
Publication Date (W3CDTF): 2004-01
Alternative Title: Behavior of irradiated BWR fuel under reactivity-initiated-accident conditions; Results of tests FK-1, -2 and -3
Periodical title: JAERI-Research 2003-033
Text Language Code: eng
Target Audience: 一般
Note (General): Boiling water reactor (BWR) fuels with burnups of 41 to 45 GWd/tU were pulse-irradiated in the Nuclear Safety Research Reactor (NSRR) to investigate fuel behavior under cold startup reactivity-initiated-accident (RIA) conditions. BWR fuel segment rods of 8$\times$8BJ (STEP I) type from Fukushima-Daiichi Unit 3 nuclear power plant were refabricated into short test rods, and they were subjected to prompt enthalpy insertion from 293 to 607 J/g (70 to 145 cal/g) within about 20 ms. The fuel cladding had enough ductility against the prompt deformation due to pellet cladding mechanical interaction. The plastic hoop strain reached 1.5\% at the peak location. The cladding surface temperature locally reached about 600 deg C. Recovery of irradiation defects in the cladding due to high temperature during the pulse irradiation was indicated via X-ray diffractometry. Fission gas release during the pulse irradiation was from 3.1\% to 8.2\%, depending on the peak fuel enthalpy and the normal operation conditions.
低温起動時の反応度事故(RIA)条件下における燃料挙動を明らかにするため、燃焼度41$\sim$45GWd/tUの沸騰水型原子炉(BWR)燃料のパルス照射実験を原子炉安全性研究炉(NSRR)において実施した。試験燃料棒は福島第一原子力発電所三号機で用いられたBWR8$\times$8BJ(STEP I)型セグメント燃料棒を短尺加工したもので、NSRRにおいて約20ms以内の短時間に293$\sim$607J/g(70$\sim$145cal/g)の熱量が与えられた。その際、燃料棒被覆管はペレット・被覆管機械的相互作用により高速に変形したが、被覆管の延性が十分高く破損には至らなかった。被覆管周方向の塑性歪は最大部で1.5\%に達した。被覆管温度は局所的に最大約600$^{\circ}$Cに達しており、X線回折測定の結果はパルス照射時の温度上昇により被覆管照射欠陥が回復したことを示していた。パルス照射による核分裂生成ガスの放出割合は、ピーク燃料エンタルピ及び定常運転条件に依存して、3.1\%$\sim$8.2\%の値であった。
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