Numerical analysis of RBHT reflood experiments using MARS 1D and 3D modules

Title
Numerical analysis of RBHT reflood experiments using MARS 1D and 3D modules
Authors
김성중
Keywords
entrainment; thermal-hydraulics; numerical simulation; LOCA; quench; rod bundle
Issue Date
2015-01
Publisher
TAYLOR & FRANCIS LTD
Citation
JOURNAL OF NUCLEAR SCIENCE AND TECHNOLOGY, v. 52, NO 1, Page. 70-84
Abstract
The Rod Bundle Heat Transfer (RBHT) program was performed experimentally to analyze the reflood heat transfer phenomena under the conditions of reflood phase following a hypothesized loss of coolant accident (LOCA) by the team of Penn State University. In order to verify the experimental data using a numerical analysis, the Multi-dimensional Analysis of Reactor Safety (MARS) assessment of the RBHT experimental data was carried out for the flooding rates of 0.0254 and 0.1524m/sec with the upper plenum pressure of 276 kPa. The RBHT experimental data of Tests 1285 and 1383 were compared with the calculation results of the MARS 1D and 3D modules. The MARS code shows a good agreement in the general trend of the peak cladding temperatures although there are limitations in predicting accurate quenching time for both modules. However, in comparison to the MARS 1D module simulation, the MARS 3D module shows the improved calculation capability in that the code can capture local enhanced heat transfer with implication of spacer grids. Moreover, the temperature profiles simulated by the 3D module show the accurate prediction at which the local peak temperatures occur. For more enhanced simulations, local flow parameters such as cross flow and vortex flow need to be analyzed for a more accurate prediction of quenching behavior.
URI
http://hdl.handle.net/20.500.11754/21597http://www.tandfonline.com/doi/full/10.1080/00223131.2014.932722?scroll=top&needAccess=true
ISSN
0022-3131
DOI
http://dx.doi.org/10.1080/00223131.2014.932722
Appears in Collections:
COLLEGE OF ENGINEERING[S](공과대학) > NUCLEAR ENGINEERING(원자력공학과) > Articles
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