Browse > Article
http://dx.doi.org/10.1016/j.net.2022.07.010

Moving reactor model for the MULTID components of the system thermal-hydraulic analysis code MARS-KS  

Hyungjoo Seo (Department of Nuclear Engineering, Seoul National University)
Moon Hee Choi (Department of Nuclear Engineering, Seoul National University)
Sang Wook Park (Department of Nuclear Engineering, Seoul National University)
Geon Woo Kim (Department of Nuclear Engineering, Seoul National University)
Hyoung Kyu Cho (Department of Nuclear Engineering, Seoul National University)
Bub Dong Chung (FNC Technology Co., Ltd.)
Publication Information
Nuclear Engineering and Technology / v.54, no.11, 2022 , pp. 4373-4391 More about this Journal
Abstract
Marine reactor systems experience platform movement, and therefore, the system thermal-hydraulic analysis code needs to reflect the motion effect on the fluid to evaluate reactor safety. A moving reactor model for MARS-KS was developed to simulate the hydrodynamic phenomena in the reactor under motion conditions; however, its applicability does not cover the MULTID component used in multidimensional flow analyses. In this study, a moving reactor model is implemented for the MULTID component to address the importance of multidimensional flow effects under dynamic motion. The concept of the volume connection is generalized to facilitate the handling of the junction of MULTID. Further, the accuracy in calculating the pressure head between volumes is enhanced to precisely evaluate the additional body force. Finally, the Coriolis force is modeled in the momentum equations in an acceleration form. The improvements are verified with conceptual problems; the modified model shows good agreement with the analytical solutions and the computational fluid dynamic (CFD) simulation results. Moreover, a simplified gravity-driven injection is simulated, and the model is validated against a ship flooding experiment. Throughout the verifications and validations, the model showed that the modification was well implemented to determine the capability of multidimensional flow analysis under ocean conditions.
Keywords
Marine reactor; System TH analysis code; MARS-KS moving reactor model; Multi-dimensional flow; Verification and validation;
Citations & Related Records
Times Cited By KSCI : 2  (Citation Analysis)
연도 인용수 순위
1 IMO MEPC72, "Resolution MEPC.304(72)", Initial IMO Strategy on Reduction of GHG Emissions from Ships, 2018.
2 J. Ovcina, in: DNV: Nuclear Power Might Offer a Pathway to Reach IMO GHG Targets, Offshore Energy, 2021. Accessed from, https://www.offshore-energy.biz/dnv-nuclear-power-might-offer-a-pathway-to-reach-imo-ghg-targets/. Feb 21th 2022.
3 J. Buongiorno, et al., The Offshore floating nuclear plant concept, Nucl. Technol. 194 (1) (2016) 1-14.   DOI
4 I.H. Kim, et al., Development of BANDI-60S for a Floating Nuclear Power Plant, Transactions of the Korean Nuclear Society Autumn Meeting, Goyang, Korea, 2019. October 24-25.
5 H. Subki, Advances in Small Modular Reactor Technology Developments, International Atomic Energy Agency, Vienna, 2018.
6 KLT-40S Overview", Advanced Reactor Information System, International Atomic Energy Agency, Vienna, 2013.
7 G. Gennaro, M. Boe, Sustainable Decarbonization of Ocean Transportation from Marine Molten Salt Reactors (M-MSR) for Zero-Emission Electric Propulsion, SNAME Maritime Convention, September, 2020.
8 M. Pater, "Multiphysics Simulations of Molten Salt Reactors Using the Moltres Code", MS Thesis, Universitat Politecnica de Catalunya, 2019 .
9 J. Devanney, et al., ThorConTM-The Do-Able Molten Salt Reactor, ThorCon USA Inc, 2018 version 1.24.
10 C. Filippone, K. Jordan, The Holos Reactor: A Distributable Power Generator with Transportable Subcritical Power Modules, 2017.
11 T. Ishida, I. Tomiai, Development of Analysis Code for Thermal Hydrodynamics of Marine Reactor under Multi-Dimensional Ship Motions, RETRAN-02/GRAV, JAERI, 1992. JAERI-M-91-226.
12 J.H. Kim, G.C. Park, Development of RETRAN-03/MOV code for thermalhydraulic analysis of nuclear reactor under moving conditions, J. Kor. Nucl. Soc. 28 (1996) 542-550.
13 J.H. Kim, T.W. Kim, S.M. Lee, G.C. Park, Study on the natural circulation characteristics of the integral type reactor for vertical and inclined conditions, Nucl. Eng. Des. 207 (2001) 21-31.   DOI
14 G.L. Mesina, D.L. Aumiller, F.X. Buschman, M.R. Kyle, Modeling moving systems with RELAP5-3D, Nucl. Sci. Eng. 182 (1) (2016) 83-95.   DOI
15 B.H. Yan, L. Yu, The development and validation of a thermal hydraulic code in rolling motion, Ann. Nucl. Energy 38 (2011) 1728-1736.   DOI
16 S.C. Tan, G.H. Su, P.Z. Gao, Heat transfer model of single-phase natural circulation flow under a rolling motion condition, Nucl. Eng. Des. 239 (2009) 2212-2216.   DOI
17 Q. Yan, et al., Effect of single and combined ocean motions on a small OFNP under SBO accidents, Ann. Nucl. Energy 145 (2020), 107564.
18 Z. Cao, et al., Effects of inclined condition on LOCA for a small offshore reactor with OTSG, Nucl. Eng. Des. 375 (2021), 111098.
19 B.J. Kim, S.W. Lee, Development of Dynamic Motion Models of SPACE Code for Ocean Nuclear Reactor Analysis, Nuclear Engineering and Technology, 2021.
20 H.K. Beom, G.W. Kim, G.C. Park, H.K. Cho, Verification and improvement of dynamic motion model in MARS for marine reactor thermal-hydraulic analysis under ocean condition, Nucl. Eng. Technol. 51 (2019) 1231-1240.   DOI
21 J.J. Jeong, K.S. Ha, B.D. Chung, W.J. Lee, Development of a multi-dimensional thermal-hydraulic system code, MARS 1.3.1, Ann. Nucl. Energy 26 (1999) 1611-1642.   DOI
22 H.K. Beom, G.W. Kim, G.C. Park, H.K. Cho, Improvement of Dynamic Motion Model in MARS-KS for Downcomer Modeling of a Maritime Reactor with Cross-Junction Connection, Transactions of the Korean Nuclear Society Spring Meeting, Jeju, Korea, 2019. May 23-24.
23 B.D. Chung, et al., "MARS Code Manual Volume 4: Developmental Assessment Report", KAERI /TR-3042/2005, Korea Atomic Energy Research Institute, 2009.
24 S.M. Lee, "Development of Two-phase Thermal-Hydraulic Model for the Prediction of Multi-Dimensional Flow Behaviors in the Best Estimate Safety Analysis of Nuclear Power Plant", PhD Thesis, Seoul National University, 2005.
25 D.H. Kang, S.W. Lee, B.D. Chung, SGTR Event Analysis of APR1400 on the Effects of Multi-D Modeling Compared with 1D Modeling Using MARS Code, Transactions of the Korean Nuclear Society Spring Meeting, Chuncheon, 2006.
26 P. Ruponen, Progressive Flooding of a Damaged Passenger Ship, Helsinki University of Technology, 2007.
27 K.S. Kim, Assessment Method of the Fitness of Initial Arrangement Design of a Naval Ship Considering Ship Flooding, PhD Thesis, Seoul National University, 2019.