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The multiple pressure tube rupture (MPTR) issue in RBMK safety technology

机译:RBMK安全技术中的多压力管破裂(MPTR)问题

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The RBMK core is constituted by more than one-thousand pressurized channels housed into stacked graphite blocks and connected at the bottom and at the top by small diameter (D) and long length (L) pipes (less than 0.01 and more than 10 m, respectively) that end up into headers and drum separators. Control valves are installed in the bottom lines. Due to the large LID value and to the presence of valves and other geometric discontinuities along the lines connecting with the pressure channels, the Fuel Channel Blockage (FCB) event is possible and already occurred in two documented NPP events. Pressure tube rupture occurred in a third NPP event not originated by FCB. Previous investigations, have shown the relevance of these events for the safety technology, and the availability of proper computational technique for the analysis, see the first and the third companion paper in this journal issue, respectively. The occurrence of the FCB event remains undetected for a few tens of seconds because of the lack of full monitoring for the individual channels, fourth companion paper in this journal issue. Therefore, fission power continues to be produced in the absence of cooling. This brings in subsequent times to fuel rod overheating, pressure tube failure, damage of the neighbouring graphite brick and ejection of damaged fuel. Following the pressure tube rupture, reactor cavity pressurization, radioactivity release into the same area and change of fluid properties occur that allow the detection of the event and cause the reactor scram at a time of a few tens of seconds depending upon the channel working conditions and the severity of the blockage. Notwithstanding the [delayed] scram and the full capability of the reactor designed safety features to keep cooled the core, the multiple pressure tube rupture (MPTR) issue is raised. The question to be answered is whether the 'explosion' of the blocked pressure tube damages not only the neighbour graphite bricks but propagates to other channels causing the potential for several channel failure. In order to address the MPTR issue fuel channel thermal-hydraulics and three-dimensional (3D) neutron kinetics analyses have been performed, as well structural mechanics calculations for the graphite bricks and rings (graphite rings surround the pressure tube to accommodate for thermal and radiation induced expansions). The bases for the analysis and the results of the study are presented. The conclusion, not reported within a licensing based format, is that the MPTR consequences are not expected to be relevant for the safety of the RBMK installations. This is supported by the analysis of experiments performed at the TKR facility available at the EREC research Centre near Moscow.
机译:RBMK堆芯由容纳在堆叠石墨块中的一千多个加压通道构成,并通过小直径(D)和长长度(L)的管道(小于0.01且大于10 m,分别),最后变成标题和鼓形分隔符。控制阀安装在底部。由于LID值较大,并且沿与压力通道连接的管线沿线存在阀门和其他几何不连续性,因此可能发生燃料通道堵塞(FCB)事件,并且已在两个已记录的NPP事件中发生。压力管破裂发生在非FCB引发的第三次NPP事件中。先前的研究已经显示了这些事件与安全技术的相关性,以及用于分析的适当计算技术的可用性,请分别参阅本期刊的第一篇和第三篇随笔。由于缺乏对各个渠道的全面监控,因此数十秒钟仍未检测到FCB事件的发生,这是该期刊的第四篇配套文章。因此,在没有冷却的情况下继续产生裂变功率。这随后导致燃料棒过热,压力管故障,相邻石墨砖的损坏以及损坏燃料的喷射。压力管破裂后,反应堆腔增压,放射性释放到同一区域,并且发生流体性质变化,这使得可以检测到该事件,并根据通道工作条件和时间在几十秒内引起反应堆破裂。堵塞的严重程度。尽管[延迟] scram和反应堆设计的安全功能具有充分的功能以保持堆芯冷却,但仍存在多压力管破裂(MPTR)的问题。要回答的问题是,受压的压力管的“爆炸”是否不仅会损坏相邻的石墨砖,还会传播到其他通道,从而导致多个通道出现故障的可能性。为了解决MPTR问题,已经对燃料通道进行了热工水力和三维(3D)中子动力学分析,并对石墨砖和环(石墨环环绕压力管以适应热和辐射)进行了结构力学计算。引起的膨胀)。介绍了分析的基础和研究结果。该结论(未以基于许可的格式进行报告)是,预计MPTR后果与RBMK安装的安全无关。莫斯科附近的EREC研究中心的TKR设施进行的实验分析支持了这一点。

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