Critical Heat Flux on Curved Calandria Vessel of Indian PHWRs During Severe Accident Condition

P. K. Verma; P. P. Kulkami; P. Pandey; S. V. Prasad; A. K. Nayak

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Critical Heat Flux on Curved Calandria Vessel of Indian PHWRs During Severe Accident Condition

机译：在严重事故情况下印度Phwrs弯曲Calandria船舶的临界热量

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In pressurized heavy water reactors (PHWRs), during an unmitigated severe accident, the absence of adequate cooling arising from multiple failures of the cooling system leads to the collapse of pressure tubes and calandria tubes, which may ultimately relocate to the lower portion of the calandria vessel (CV) forming a debris bed. Due to the continuous generation of decay heat in the debris, it will melt and form a molten pool at the bottom of the CV. The CV is surrounded by calandria vault water, which acts as a heat sink at this scenario. In-vessel corium retention (IVR) through the external reactor vessel cooling (ERVC) is conceived as an effective method for maintaining the integrity of a calandria vessel during a severe accident in a nuclear power plant. Under the IVR conditions, it is necessary to ensure that the imparted heat flux due to melt is less than the critical heat flux (CHF) at the bottom of the calandria vessel wall. To evaluate the thermal margin for IVR, experiments are performed in a prototypic curved section of calandria vessel (25o sector) of calandria vessel to determine the CHF, heat transfer coefficient, and its variation along with the curvature of calandria vessel. The effect of moderator drainpipe on CHF and the heat transfer coefficient has also been evaluated. It has been observed that the imparted heat flux is much less than the CHF at the bottom of the calandria vessel.

机译：在加压重水反应器（PHWR）中，在未发生的严重事故中，从冷却系统的多次故障引起的缺乏充分的冷却导致压力管和Calandria管的崩溃，这最终可能搬迁到Calandria的下部血管（CV）形成碎片床。由于碎屑中腐烂的衰减热量不断发热，它将在CV底部熔化并形成熔池。 CV被Calandria Vault水包围，在这种情况下充当散热器。通过外部反应器血管冷却（ERVC）的血管内芯（IVR）被认为是在核电站的严重事故中维持Calandria船舶完整性的有效方法。在IVR条件下，必须确保由于熔体引起的赋予热通量小于Calandria船壁底部的临界热通量（CHF）。为了评估IVR的热裕度，实验是在Calandria容器的Calandria容器（250扇区）的原型曲面中进行的实验，以确定CHF，传热系数及其变化以及Calandria船的曲率。还评估了主持人排水管对CHF和传热系数的影响。已经观察到赋予的热通量远小于Calandria船只底部的CHF。

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来源
《Journal of Heat Transfer》 |2021年第2期|022101.1-022101.9|共9页
作者
P. K. Verma; P. P. Kulkami; P. Pandey; S. V. Prasad; A. K. Nayak;
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作者单位

Department of Engineering Sciences Homi Bhabha National Institute Trombay Mumbai 400094 India Reactor Engineering Division Bhabha Atomic Research Centre Mumbai 400085 India;

Reactor Engineering Division Bhabha Atomic Research Centre Mumbai 400085 India;

Reactor Engineering Division Bhabha Atomic Research Centre Mumbai 400085 India;

Department of Engineering Sciences Homi Bhabha National Institute Trombay Mumbai 400094 India Reactor Engineering Division Bhabha Atomic Research Centre Mumbai 400085 India;

Department of Engineering Sciences Homi Bhabha National Institute Trombay Mumbai 400094 India Reactor Engineering Division Bhabha Atomic Research Centre Mumbai 400085 India;

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收录信息美国《科学引文索引》(SCI);美国《工程索引》(EI);
原文格式 PDF
正文语种 eng
中图分类
关键词
critical heat flux (CHF); downward facing curved surface; calandria vessel; severe accident; drainpipe; PHWRs;

机译：临界热通量（CHF）;面向弯曲的表面;Calandria船;严重事故;排水管;phwrs.;

Critical Heat Flux on Curved Calandria Vessel of Indian PHWRs During Severe Accident Condition

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