Passive Containment Cooling System (PCCS) response with Drywell Gas Recirculation System (DGRS) activated during a severe accident scenario with release of non-condensable gas

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• 作者：Domenico Paladino ; ^{domenico.paladino@psi.ch} ; Jö ; rg Dreier
• 刊名：Nuclear Engineering and Design
• 出版年：2012
• 期刊代码：132_00295493
• 类别：et
• 出版时间：June, 2012
• 卷：247
• 期：Complete
• 页码：212-220
• 文件大小：1300 K

摘要

The paper presents the experimental results of an integral containment test named T2.1 performed in the PANDA facility. Test T2.1 investigated the effect of a Drywell Gas Recirculation System (DGRS) activation on a Passive Containment Cooling System (PCCS), during a postulated severe accident with release of hydrogen later during the transient (in PANDA facility Helium is used to simulate hydrogen). The containment initial thermal-hydraulic conditions (e.g. temperature, pressure, gas composition, decay heat, etc.) in test T2.1 represent the situation predicted at 1 h after a Loss of Coolant Accident (LOCA) for a specific ESBWR design. Test T2.1 simulated the decay heat which would be released during a transient of about 12.5 h, including structural heat release in the early phase. Test T2.1 includes four main phases. The first phase, lasting for about 10,000 s simulated a LOCA 1 h after SCRAM. The second phase, helium was injected for about 7200 s and the DGRS was activated. The third phase was carried on from 17,200 s to about 43,200 s by keeping the DGRS in operation. In the fourth phase the DGRS was switched off and was observed the PCCS response.