Analysis of Status Fourteen Hours after All Power Loss at the Fukushima Daiichi Nuclear Power Plant Unit 1

Q4 Engineering
Tsuyoshi Matsuoka
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Abstract

The author independently conducted a detailed analysis of plant conditions, based on a new meltdown process, during the 14 hours after all power loss at the Fukushima Daiichi Nuclear Power Plant Unit 1. After 3 : 30 PM on March 11, 2011, all power loss caused reactor core cooling function loss and the vaporization of water in the reactor vessel ( RPV ) , and the RPV was filled with high-temperature hydrogen gas generated by decay heat and Zr - H 2 O reactions. The reactor core melted and the periph-eral stainless-steel structures and nuclear vessel walls were heated by the radiation energy of decay heat. Then, the shrouds and other components near the reactor core started melting and the wall temperature of the RPV was raised. Along with the wall temperature rising to nearly 650 ℃ , the aluminum insulation near the wall started melting ( aluminum melting point, about 650 ℃) . The heat from the collapsed insulation caused the superheated state of the containment pressure and temperature of 0.84 MPa and 400 ℃ , respectively, around 3 AM from the saturated state of 0.6 MPa around 1 AM on March 12. After that, the containment vessel was depressurized gradually and kept under stable cooling 14 hours after all power loss, for the time from 4 to 6 AM. By the first water injection to the reac tor core at 4 AM, radioactivity release increased slightly and the containment pressure was stable. However, the situation changed significantly after continuous water injection to the reactor core start ed at around 6 AM. The water injection into the high-temperature reactor core generated film boiling ( poor heat transfer ) and good reactor core cooling was no longer available; thus, increased heating by the Zr - H 2 O reactions started. The results of the author’s analysis showed good consistency with the measured reactor pressure, containment pressure, containment temperature and radioactivity near the main gate. Although decay heat cannot be decreased intentionally, the occurrence of the Zr - H 2 O reactions can be inhibited. It is proposed that the best way to mitigate the effects of a meltdown is to stop water injection to the core after detecting the initiation of film boiling or inferring that the fuel rods are not covered with water.
福岛第一核电站1号机组全部断电14小时后的状况分析
作者在福岛第一核电站1号机组全部断电后的14小时内,根据一个新的熔毁过程,独立地对电站状况进行了详细的分析。2011年3月11日下午3时30分以后,全部功率损失导致堆芯冷却功能丧失,反应堆容器(RPV)内的水蒸发,RPV内充满衰变热和Zr - h2o反应产生的高温氢气。反应堆堆芯熔化,外围不锈钢结构和核容器壁被衰变热的辐射能加热。然后,堆芯附近的罩壳和其他部件开始熔化,RPV的壁温升高。随着壁面温度上升到接近650℃时,靠近壁面的保温铝开始熔化(铝的熔点,约650℃)。3月12日凌晨1点左右,隔热层坍塌产生的热量使安全壳压力和温度从0.6 MPa的饱和状态分别在凌晨3点左右达到0.84 MPa和400℃的过热状态。在此之后,安全壳逐渐减压,并在所有断电后的14小时内保持稳定冷却,时间为上午4点至6点。上午4点第一次向堆芯注水时,放射性释放略有增加,安全壳压力稳定。然而,在早上6点左右开始向反应堆堆芯持续注水后,情况发生了显著变化。高温堆芯注水产生的膜沸腾(传热差)和良好的堆芯冷却不再有效;因此,Zr - h2o反应开始升温。作者的分析结果与主闸口附近测量到的反应堆压力、安全壳压力、安全壳温度和放射性具有良好的一致性。虽然不能有意地降低衰变热,但可以抑制Zr - h2o反应的发生。建议减轻熔毁影响的最佳方法是在检测到膜沸腾的开始或推断燃料棒没有被水覆盖后停止向堆芯注水。
本文章由计算机程序翻译,如有差异,请以英文原文为准。
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来源期刊
Transactions of the Atomic Energy Society of Japan
Transactions of the Atomic Energy Society of Japan Energy-Nuclear Energy and Engineering
CiteScore
0.50
自引率
0.00%
发文量
16
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