A loss of coolant accident (LOCA) in a PWR (pressurized water reactor) would generate debris from thermal insulation and other materials in the vicinity of the break. It is postulated that debris can transported to the containment sump strainer. Some of the debris may pass through the strainer and could challenge the long-term core cooling capability of the plant. To address this safety issue, the downstream effect tests for the PWR were performed. Sensitivity studies on pressure drops through LOCA-generated debris deposited on a fuel assembly were performed to evaluate the effects of debris type and flow rate. Fibrous debris is the most crucial material in terms of causing pressure drops.
- Nuclear Engineering Division
Experimental Study of Debris-Loading Head Loss Test for PWR Fuel Assembly After LOCA
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Wang, D, Niu, F, Zhuo, W, Ren, J, Guo, Z, & Bhatti, HA. "Experimental Study of Debris-Loading Head Loss Test for PWR Fuel Assembly After LOCA." Proceedings of the 2017 25th International Conference on Nuclear Engineering. Volume 4: Nuclear Safety, Security, Non-Proliferation and Cyber Security; Risk Management. Shanghai, China. July 2–6, 2017. V004T06A024. ASME. https://doi.org/10.1115/ICONE25-67185
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