Image-processing of time-averaged interface distributions representing CCFL characteristics in a large scale model of a PWR hot-leg pipe geometry
Sign Up to like & getrecommendations! Published in 2017 at "Annals of Nuclear Energy"
DOI: 10.1016/j.anucene.2017.01.021
Abstract: Abstract Countercurrent Flow Limitation (CCFL) was experimentally investigated in a 1/3.9 downscaled COLLIDER facility with a 190 mm pipe’s diameter using air/water at 1 atmospheric pressure. Previous investigations provided knowledge over the onset of CCFL mechanisms.… read more here.
Keywords: ccfl characteristics; time averaged; hot leg; ccfl ... See more keywords
Investigation of the reactor heat transfer function between the cold and the hot leg of the primary circuit
Sign Up to like & getrecommendations! Published in 2019 at "Annals of Nuclear Energy"
DOI: 10.1016/j.anucene.2018.10.013
Abstract: Abstract In this paper the propagation mechanism of the temperature fluctuations of the coolant is investigated using the measured hot and cold leg temperature signals of the primary loops of a VVER-440 reactor. The aim… read more here.
Keywords: hot leg; transfer function; reactor heat; heat transfer ... See more keywords
Uncertainty analysis of ROSA/LSTF test by RELAP5 code and PKL counterpart test concerning PWR hot leg break LOCAs
Sign Up to like & getrecommendations! Published in 2018 at "Nuclear Engineering and Technology"
DOI: 10.1016/j.net.2018.05.005
Abstract: Abstract An experiment was conducted for the OECD/NEA ROSA-2 Project using the large-scale test facility (LSTF), which simulated a 17% hot leg intermediate-break loss-of-coolant accident in a pressurized water reactor (PWR). In the LSTF test,… read more here.
Keywords: hot leg; lstf test; test; uncertainty analysis ... See more keywords
Droplets entrainment ratio in a PWR hot-leg pipe geometry
Sign Up to like & getrecommendations! Published in 2018 at "Nuclear Engineering and Design"
DOI: 10.1016/j.nucengdes.2018.01.010
Abstract: Abstract Droplets entrainment was found to contribute to the occurrence of countercurrent flow limitation (CCFL) at COLLIDER test facility which has a PWR hot-leg pipe geometry with a large diameter value of 190 mm. Previous investigations… read more here.
Keywords: hot leg; entrainment ratio; geometry; droplets entrainment ... See more keywords
Uncertainty calculation in small break LOCA in the emergency core cooling system connected to the hot leg of Angra 2 nuclear power plant
Sign Up to like & getrecommendations! Published in 2018 at "International Journal of Nuclear Energy Science and Technology"
DOI: 10.1504/ijnest.2018.094284
Abstract: Owing to the occurrence of nuclear accidents, worldwide nuclear regulatory organisations included the analysis of accidents considered as design basis accidents - Loss of Coolant Accident (large and small-break, LBLOCA or SBLOCA) - in the… read more here.
Keywords: emergency core; cooling system; small break; angra nuclear ... See more keywords