AP1000啟動(dòng)給水在非LOCA事故下的衰變熱排出性能分析
本文選題:AP + 非LOCA。 參考:《核動(dòng)力工程》2015年06期
【摘要】:為驗(yàn)證三代核電AP1000核電廠在非LOCA事故工況下,啟動(dòng)給水補(bǔ)給性能是否滿足衰變熱排出的縱深防御準(zhǔn)則,保守認(rèn)為事故發(fā)生后,反應(yīng)堆停堆,廠用電及外電網(wǎng)喪失,主給水喪失,凝汽器熱阱喪失,蒸汽發(fā)生器背壓為安全閥最低整定壓力,蒸汽發(fā)生器與啟動(dòng)給水泵均為單列可用。首先,驗(yàn)證凝結(jié)水儲(chǔ)箱處于最低液位時(shí),啟動(dòng)給水的最低補(bǔ)給能力能否滿足不小于118.1 m3/h的準(zhǔn)則要求;其次,論證事故后由于備用交流電源加載滯后而導(dǎo)致啟動(dòng)給水延后140 s投運(yùn),蒸汽發(fā)生器依靠自身緩沖水裝量能否帶走衰變熱而不觸發(fā)專設(shè)安全系統(tǒng);再次,論證140 s后啟動(dòng)給水最低補(bǔ)給流量,能否穩(wěn)定蒸汽發(fā)生器液位并使其回升;最后,驗(yàn)證凝結(jié)水儲(chǔ)箱縱深防御水裝量能否滿足啟動(dòng)給水24 h連續(xù)補(bǔ)給的準(zhǔn)則要求。本文通過(guò)對(duì)啟動(dòng)給水最低補(bǔ)給流量、蒸汽發(fā)生器緩沖水裝量、啟動(dòng)給水液位控制,以及凝結(jié)水儲(chǔ)箱水裝量的保守計(jì)算分析,驗(yàn)證了AP1000啟動(dòng)給水在非失水事故(Non-LOCA)事故下衰變熱排出功能設(shè)計(jì)的可靠性以及與縱深防御準(zhǔn)則的一致性。
[Abstract]:In order to verify whether the recharge performance of AP1000 nuclear power plant under non-LOCA accident conditions meets the criterion of deep defense of decay heat emission, it is considered that after the accident, reactor shutdown, loss of power supply and external power network, loss of main feed water, The condenser heat trap is lost, the back pressure of the steam generator is the lowest setting pressure of the safety valve, and the steam generator and the starting feed pump are both available in single row. First, verify that when the condensate tank is at the lowest liquid level, can the minimum recharge capacity of the starting water meet the criterion requirement of not less than 118.1 m3 / h; secondly, It is demonstrated that after the accident the starting water supply is delayed for 140 s due to the delayed loading of the standby AC power supply, and whether the steam generator can take away the decay heat without triggering the specially designed safety system depending on its own buffer water capacity; thirdly, It is demonstrated that the minimum recharge flow of feed water can stabilize the liquid level of steam generator and make it rise after 140 s. Finally, it is verified that the quantity of condensate tank can meet the requirement of starting supply water supply for 24 hours. In this paper, the minimum recharge flow of starting feed water, the buffer water volume of steam generator, the level control of starting feed water, and the conservative calculation of water volume of condensate storage tank are analyzed. The reliability of the design of the decay heat discharge function of AP1000 starting feed water under Non-LOCA (Non-LOCA) accident is verified, and the reliability of the design and the consistency with the depth defense criterion are verified.
【作者單位】: 深圳中廣核工程設(shè)計(jì)有限公司上海分公司;
【分類號(hào)】:TM623.8
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