Study on Accident Mitigation and Cooling of Damaged Core during Severe Accident of Right Water Nuclear Reactor

右水核反应堆严重事故中事故缓解及受损堆芯冷却研究

基本信息

批准号：
12650213
负责人：
KOIZUMI Yasuo
金额：
$ 2.3万
依托单位：
Kogakuin University
依托单位国家：
日本
项目类别：
Grant-in-Aid for Scientific Research (C)
财政年份：
2000
资助国家：
日本
起止时间：
2000 至 2002
项目状态：
已结题

来源：
https://kaken.nii.ac.jp/grant/KAKENHI-PROJECT-12650213/
关键词：
Severe Accident in Light Water Reactor Accident Management Debris Cooling Reactor Pressure Vessel Wall Cooling Water Penetration into Narrow Space Two-Phase Flow Counter-Current Flow Limiting (CCFL)Critical Heat Flux (CHF)

项目摘要

Quenching of a thin gap annular flow passage by gravitational liquid penetration was examined experimentally by using R-113. The outer wall was made of copper. The inner wall was made of copper or glass. The inner diameters of the outer wall of the annular flow passages were 40 and 41 mm and the outer diameters of the inner wall were 38, 36 and 30 mm. By combining these, the annular gap spacings tested were 0.3, 0.5, 1.0, 2.0 and 5.0 mmTwo-types of experiments were performed; 1 bottom-closed experiments where vapor generated flowed upward counter-currently, and 2 bottom-open experiments where liquid drained from the bottom and vapor generated flowed upward. The wall was heated up to 250℃ initially, and then liquid was directed to the test section top to flow down into the test sectionResults obtained were(1) Quenching was observed for the gap spacing б ≧ 1.0 mm. When the spacing б < 1.0 mm, the wall was gradually and monotonously cooled down without any quenching. When the bottom of th … More e flow channel was closed and the gap spacing б ≧ 2.0 mm, liquid fell down into the flow passage without quenching the hot wall and accumulated in the flow channel. Then, the hot wall quenching proceeded upward from the bottom with the accumulation of liquid. When б = 1.0 mm, the quenching propagated downward from the top(2) Overall trend observed in unheated glass inner-wall experiments and heated inner-wall experiments were fundamentally same(3) The relation between the wall super heat and the wall heat flux was quite similar to the boiling curve of the usual pool boiling. The heat flux during the film and the transition boiling period and the peak heat flux decreased as the gap spacing became narrow(4) Quenching simulation was performed by solving the two-dimensional and unsteady heat conduction equation imposing the boiling curve on the inner heat transfer surface・If the relation between the surface temperature and the heat flux is properly given, the quenching propagation is adequately reproduced・The quenching velocity is roughly correlated with Pe and Bi numbers Less

通过使用R-113对重力液体穿透进行了稀薄的间隙环流通过的淬灭。外墙是由铜制成的。内壁是由铜或玻璃制成的。环形流通道的外壁的内径为40和41毫米，内壁的外径为38、36和30 mm。通过组合这些测试的环形间隙间距为0.3、0.5、1.0、2.0和5.0 mmtwo型实验。 1个底部关闭的实验，其中蒸气产生了向上流动，而2个底部开放的实验，其中液体从底部排出，蒸气产生的液体向上流动。最初将壁加热至250°，然后将液体定向到测试部分的顶部，以向下流入所获得的测试部分，为（1）脉冲间距quench quenching。当间距<1.0毫米时，壁逐渐被单调冷却而无需淬火。当底部的底部关闭了更多的E流通道，并且间隙间距π2.0 mm，液体掉入流中，而无需淬灭热壁并积聚在流动通道中。然后，随着液体的加速，热墙淬灭从底部向上进行。当= 1.0 mm时，在未经加热的玻璃内壁实验中观察到的淬火从顶部（2）向下传播的整体趋势和加热的内壁实验从根本上相同（3）壁超热量与壁热量之间的关系与常规池沸腾的沸腾曲线非常相似。膜期间和过渡沸腾期间的热通量以及峰热通量随着间隙间隙变得狭窄而降低（4）淬火模拟是通过求解二维且不稳定的热传导方程来执行的，从而使沸腾曲线在表面温度和热量之间适当地给出了quage的相关性，如果quage的关系是正确的，如果quage的关系是适当的，如果是在quagient上，如果是quage的quage，则dequence是quage的频率，而又有频率依次。与PE和BI数大致相关