Static and transient analyses of Advanced Power Reactor 1400 (APR1400) initial core using open-source nodal core simulator KOMODO

다국어 초록 (Multilingual Abstract)

The United Arab Emirates is currently building and operating four units of the APR-1400 developed by aSouth Korean vendor, Korea Electric Power Corporation (KEPCO). This paper attempts to perform APR1400 reactor core analysis by using the well-known two-step method. The two-step method wasapplied to the APR-1400 first cycle using the open-source nodal diffusion code, KOMODO. In this study,the group constants were generated using CASMO-4 fuel transport lattice code. The simulation wasperformed in Hot Zero Power (HZP) at steady-state and transient conditions. Some typical parametersnecessary for the Nuclear Design Report (NDR) were evaluated in this paper, such as effective neutronmultiplication factor, control rod worth, and critical boron concentration for steady-state analysis. Otherparameters such as reactivity insertion, power, and fuel temperature changes during the ReactivityInsertion Accident (RIA) simulation were evaluated as well. The results from KOMODO were verifiedusing PARCS and SIMULATE-3 nodal core simulators. It was found that KOMODO gives an excellentagreement

참고문헌 (Reference)

1 K. Barr, "Verification of MPACT for the APR1400 Benchmark" Nuclear Reactor Analysis & Methods Group, University of Michigan 2020

2 J. Lepp€anen, "The serpent Monte Carlo code: status, development and applications in 2013" 82 : 142-150, 2015

3 Studsvik Scandpower Inc, "SIMULATE-3 Advanced Three-Dimensional Two-Group Reactor Analysis Code" Studsvik Scandpower Inc 2009

4 J. Choe, "Performance evaluation of Zircaloy reflector for pressurized water reactors" 40 (40): 160-167, 2016

5 M. Imron, "PWR MOX/UO2 transient benchmark calculation using Monte Carlo serpent 2 code and open nodal core simulator ADPRES" 7 (7): 031603-, 2020

6 T. Kozlowski, "PWR MOX/UO2 Core Transient Benchmark vol. 20" Nuclear Energy Agency, OECD 2006

7 T. Downar, "PARCS: Purdue advanced reactor core simulator" 7-10, 2002

8 P. K. Romana, "OpenMC : a state-of-the-art Monte Carlo code for research and development" 82 : 90-97, 2015

9 V. G. Zimin, "Nodal neutron Kinetics model based on nonlinear iteration Procedure for LWR analysis" 25 (25): 507-528, 1998

10 D. J. Siefman, "Full core modeling techniques for research reactors with irregular geometries using serpent and PARCS applied to the CROCUS reactor" 85 : 434-443, 2015

11 M. Imron, "Development and verification of open reactor simulator ADPRES" 133 : 580-588, 2019

12 Li Z., "Development and verification of PWR core transient coupling calculation software"

13 F. Y. Odeh, "Core design optimization and analysis of the Purdue novel modular reactor(NMR-50)" 94 : 288-299, 2016

14 Studsvik Scandpower Inc, "CASMO-4 A Fuel Assembly Burnup Program User's Manual" Studsvik Scandpower Inc 2009

15 F. Fejt, "Analysis of a small-scale reactor core with PARCS/serpent" 117 : 25-31, 2018

16 S. Yuk, "APR-1400 Reactor Core Benchmark Problems" KAERI 2019