Small break loss of coolant accident (SBLOCA) of a nuclear power plant reactor primary system is simulated at the high pressure integral test facility (HPITF). The break is loca ted at the bottom of the horizontal cold leg and its area is 1% (NSB 7 case).

 
  • 在高壓綜合實(shí)驗裝置(HPITF)上進(jìn)行核電廠(chǎng)反應堆一次系統冷管段小破口失水事故(SBLO-CA)模擬實(shí)驗,破口方向為冷管段底部,破口面積為1%25(NSB-7工況)。
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