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다국어 초록 (Multilingual Abstract)

As passive safety features for nuclear power plants receive increasing attention, various studies have been conducted to
develop safety systems for 3rd-generation (GEN-III) nuclear power plants that are driven by passive systems. The Passive
Auxiliary Feedwater System (PAFS) is one of several passive safety systems being designed for the Advanced Power Reactor
Plus (APR+), and extensive studies are being conducted to complete its design and to verify its feasibility. Because the PAFS
removes decay heat from the reactor core under transient and accident conditions, it is necessary to evaluate the heat removal
capability of the PAFS under hypothetical accident conditions. The heat removal capability of the PAFS is strongly dependent
on the heat transfer at the condensate tube in Passive Condensation Heat Exchanger (PCHX). To evaluate the model of heat
transfer coefficient for condensation, the Multi-dimensional Analysis of Reactor Safety (MARS) code is used to simulate the
experimental results from PAFS Condensing Heat Removal Assessment Loop (PASCAL). The Shah model, a default model
for condensation heat transfer coefficient in the MARS code, under-predicts the experimental data from the PASCAL. To
improve the calculation result, The Thome model and the new version of the Shah model are implemented and compared with
the experimental data.

다국어 초록 (Multilingual Abstract)

As passive safety features for nuclear power plants receive increasing attention, various studies have been conducted todevelop safety systems for 3rd-generation (GEN-III) nuclear power plants that are driven by passive systems. The PassiveAuxiliary Feedwater System (PAFS) is one of several passive safety systems being designed for the Advanced Power ReactorPlus (APR+), and extensive studies are being conducted to complete its design and to verify its feasibility. Because the PAFSremoves decay heat from the reactor core under transient and accident conditions, it is necessary to evaluate the heat removalcapability of the PAFS under hypothetical accident conditions. The heat removal capability of the PAFS is strongly dependenton the heat transfer at the condensate tube in Passive Condensation Heat Exchanger (PCHX). To evaluate the model of heattransfer coefficient for condensation, the Multi-dimensional Analysis of Reactor Safety (MARS) code is used to simulate theexperimental results from PAFS Condensing Heat Removal Assessment Loop (PASCAL). The Shah model, a default modelfor condensation heat transfer coefficient in the MARS code, under-predicts the experimental data from the PASCAL. Toimprove the calculation result, The Thome model and the new version of the Shah model are implemented and compared withthe experimental data.

참고문헌 (Reference)

1 C. H. Song, "Thermal-hydraulic R&Ds for the APR+ Developments in Korea" 2010

2 B. U. Bae, "Scaling analysis of separate effect test loop (PASCAL) for PAFS (Passive Auxiliary Feedwater System)" 2010

3 KYOUNG-HO KANG, "SEPARATE AND INTEGRAL EFFECT TESTS FOR VALIDATION OF COOLING AND OPERATIONAL PERFORMANCE OF THE APR+ PASSIVE AUXILIARY FEEDWATER SYSTEM" 한국원자력학회 44 (44): 597-610, 2012

4 "RELAP5/MOD3 Code Manual Volume IV: Models and Correlations"

5 B. J. Yun, "Construction Report of Separate Effect Test Facility for PAFS" Korea Atomic Energy Research Institute 2010

6 J. R. Thom, "Condensation in Horizontal Tube, Part 2: New Heat Transfer Model Based on Flow Regime" 46 : 3365-3387, 2003

7 J. R. Thom, "Condensation in Horizontal Tube, Part 1: Two-phase Flow Pattern Map" 46 : 3349-3363, 2003

8 Y. J. Cho, "Analytical Studies on Separate-effect Test for the Passive Auxiliary Feedwater System (PAFS) using MARS Code" 2012

9 M. M. Shah, "An Improved and Extented General Correlation for Heat Transfer During Condensation in Plain Tubes" 15 (15): 889-913, 2009

10 D. Biberg, "An Explicit Approximation for the Wetted Angle in Two-phase Stratified Pipe Flow" 77 : 1221-1224, 1999