Details

Autor(en) / Beteiligte

• Wang, Gang
• Kuang, Bo
• Zhao, Yu
• Han, Shilei
• Liu, Pengfei
• Hou, Jieming

Titel

Experimental investigation on critical heat flux of IVR-ERVC system under the natural circulation condition

Ist Teil von

• International journal of thermal sciences, 2024-01, Vol.195, p.108639, Article 108639

Ort / Verlag

Elsevier Masson SAS

Erscheinungsjahr

2024

Link zum Volltext

Quelle

Elsevier ScienceDirect Journals Complete

Beschreibungen/Notizen

• In vessel retention (IVR) of molten core debris by external reactor vessel cooling (ERVC) has been adopted as one of the important severe accident mitigation strategies for many new generation nuclear power plant designs. A one-dimensional full-height test facility was established to investigate the heat transfer limit on the outer surface of reactor pressure vessel for IVR-ERVC system under natural circulation condition. In this test facility, a one-dimensional elliptical heating block was used to simulate the lower head of reactor pressure vessel(RPV). The critical heat flux (CHF) under different operating conditions along this one-dimensional heating block were measured, to investigate the sensitivity of heat transfer limit. Experimental results show that the increase of liquid level and subcooling of coolant are beneficial to the improvement of CHF. While, the increase of flow resistance in the test facility has little effect on CHF. On the other hand, experimental results show that the influence of flow channel size on CHF is complex. CHF does not change monotonically with the increase of flow channel size. Compared with the round heating block, the CHF distribution along the heating surface is the same basically. In addition, the results of normalized analysis indicate that CHF is mainly affected by the two-phase behavior near the heating surface. These results are expected to improve the understanding of different practical engineered factors’ influence on IVR-ERVC system performance.