2013
DOI: 10.1016/j.anucene.2013.07.005
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A numerical study for the effect of flow skirt geometry on reactor internal flow

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Cited by 17 publications
(2 citation statements)
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“…The mass flow rates in center fuel assemblies are higher than that in peripheral fuel assemblies at core inlets [13]. Many researchers have made detailed analysis on the coolant mixing in the reactor, flow field in the reactor pressure vessel, flow distribution at core inlets using CFD methods [14][15][16][17][18][19][20][21][22], however the behavior of single pellet in a reactor nuclear, PWR type, due to variation on inlet temperature and mass flow rate has not been investigated as a fundamental study.…”
Section: Introductionmentioning
confidence: 99%
“…The mass flow rates in center fuel assemblies are higher than that in peripheral fuel assemblies at core inlets [13]. Many researchers have made detailed analysis on the coolant mixing in the reactor, flow field in the reactor pressure vessel, flow distribution at core inlets using CFD methods [14][15][16][17][18][19][20][21][22], however the behavior of single pellet in a reactor nuclear, PWR type, due to variation on inlet temperature and mass flow rate has not been investigated as a fundamental study.…”
Section: Introductionmentioning
confidence: 99%
“…Therefore, detailed knowledge of core inlet flow distribution under such circumstances is necessary for the design and/or improvement of the FDD. In this aspect, the computational fluid dynamics(CFD) approach is now considered as a promising tool for the understanding of local phenomena in PWR downcomer and lower plenum, prediction of pressure drop, improvement of mixing vane design, and thermal-hydraulic analysis of reactor internals (Lee and Bang, 2014;Bae and Kim, 2013;Xu and Michael, 2012;Michael and Regina, 2010;Rohde and Hohne, 2007;Lee and Bang, 2013), and thus is attractive for many engineers concerned with a short design cycle and feasibility. This paper presents a detailed evaluation performed on lower plenum design in a pressurized water reactor.…”
Section: Introductionmentioning
confidence: 99%