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contributor authorChull Jo, Jong
contributor authorKi Min, Bok
contributor authorJun Jeong, Jae
date accessioned2017-11-25T07:19:06Z
date available2017-11-25T07:19:06Z
date copyright2016/1/12
date issued2017
identifier issn0094-9930
identifier otherpvt_139_03_031305.pdf
identifier urihttp://138.201.223.254:8080/yetl1/handle/yetl/4235584
description abstractThis paper presents an evaluation of the applicability of a numerical analysis model to the transient thermal-hydraulic response of steam generator (SG) secondary side to blowdown following a steam line break (SLB) at a pressurized water reactor (PWR). To do this, the numerical analysis model was applied to simulate the same blowdown situation as in an available experiment which was conducted for a simplified SG blowdown model, and the numerical results were compared with the measurements. As a result, both are in reasonably good agreement with each other. Consequently, the present numerical analysis model is evaluated to have the applicability for numerical simulations of the transient phase change heat transfer and flow situations in PWR SGs during blowdown following a SLB.
publisherThe American Society of Mechanical Engineers (ASME)
titleEvaluation of a Numerical Analysis Model for the Transient Response of Nuclear Steam Generator Secondary Side to a Sudden Steam Line Break
typeJournal Paper
journal volume139
journal issue3
journal titleJournal of Pressure Vessel Technology
identifier doi10.1115/1.4035130
journal fristpage31305
journal lastpage031305-7
treeJournal of Pressure Vessel Technology:;2017:;volume( 139 ):;issue: 003
contenttypeFulltext


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