Experimental study and validation of MARS code for CCFL in passive emergency core cooling system (PECCS) of public acceptable simple SMR (PASS) system

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KAIST has developed a public acceptable simple SMR (PASS) system that applies the safety-related design characteristics of high temperature gas-cooled reactors (HTGR) to a water-cooled reactor. There is a new innovative safety system for decay heat removal, a passive emergency core cooling system (PECCS), in PASS. Countercurrent flow limitation (CCFL) is the most influential phenomena appearing in PASS-PECCS. In order to understand the CCFL phenomena appearing in the PASS-PECCS, down- scaled experiments were conducted in air/water conditions. From experimental study, we found that water head in an upper tank enhances water penetration into a lower tank compared with no water head case and there is an optimal water head condition. For a full-scale simulation of the PASS system using the MARS code, we proposed a new methodology simulating the CCFL phenomena without CCFL correlations and validated the nodal methodology with the results of the down-scaled experiments.
Publisher
American Nuclear Society
Issue Date
2015-08
Language
English
Citation

16th International Topical Meeting on Nuclear Reactor Thermal Hydraulics, NURETH 2015, pp.1848 - 1857

URI
http://hdl.handle.net/10203/314795
Appears in Collection
NE-Conference Papers(학술회의논문)
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