http://chineseinput.net/에서 pinyin(병음)방식으로 중국어를 변환할 수 있습니다.
변환된 중국어를 복사하여 사용하시면 됩니다.
원자력발전소 피동 노내 냉각계통 적용을 위한 유압 제어봉 구동시스템 설계
김인국(In Guk Kim),방인철(In Cheol Bang) 대한기계학회 2018 대한기계학회 춘추학술대회 Vol.2018 No.12
To enhance the safety of the nuclear power plants, a passive in-core cooling system (PINCs) is currently being studied for the various reactor types such as PWR, SMR, Gen. IV reactors in UNIST. A PINCs consists of hybrid control rod assemblies, a hydraulic control rod drive mechanism, and a natural circulation loop to remove the decay heat from the nuclear fuels. In PINCs, one of the key elements is the hydraulically driven rod control system that is being studied for their various benefits, including a) ability to be in-vessel control, b) short length of the control rods, and c) safe reactor shutdown. In this paper, a novel hydraulic rod control system was designed and tested. The tests of the hydraulic rod control system with 4-hybrid control rod were conducted with the different weight and geometry. The theoretical models of the steady flow and transient behavior were driven by the force-induced patterned geometry of the cylinder. The experimental results showed that the position of the hydraulic system with control rod was well predicted by the theoretical model within ±8.6%. Finally, this study shows the unique feature of the hydraulically driven system and its behavioral characteristics.