http://chineseinput.net/에서 pinyin(병음)방식으로 중국어를 변환할 수 있습니다.
변환된 중국어를 복사하여 사용하시면 됩니다.
원자로 가상사고시(노심) 용융물 고압 분출 모의 실험 연구
정한원,김도형,이규정,김상백,박래준,김희동,Jeong, Han-Won,Kim, Do-Hyeong,Lee, Gyu-Jeong,Kim, Sang-Baek,Park, Rae-Jun,Kim, Hui-Dong 대한기계학회 2000 大韓機械學會論文集B Vol.24 No.11
Simulated experiments of high pressure melt ejection(HPME) are performed to measure the released fraction of corium simulant from the French type PWR cavity. The experiments are carried out on a 1/20th linear scaled model of the Ulchin 1&2 cavity. Water or woods metal and nitrogen is used as simulant of molten corium and steam, respectively. Experimental parameters are water mass, annulus area and breach size. It is shown that only breach size effects is very important while the mass and the annulus area do not affect the released fraction. It is found that the liquid film transport is much more dominant mechanism than the entrainment droplet transport, especially in linear scale down simulated HPME experiment.