Browse > Article
http://dx.doi.org/10.1016/j.net.2019.02.018

Verification and improvement of dynamic motion model in MARS for marine reactor thermal-hydraulic analysis under ocean condition  

Beom, Hee-Kwan (Department of Nuclear Engineering, Seoul National University)
Kim, Geon-Woo (Department of Nuclear Engineering, Seoul National University)
Park, Goon-Cherl (Department of Nuclear Engineering, Seoul National University)
Cho, Hyoung Kyu (Department of Nuclear Engineering, Seoul National University)
Publication Information
Nuclear Engineering and Technology / v.51, no.5, 2019 , pp. 1231-1240 More about this Journal
Abstract
Unlike land-based nuclear power plants, a marine or floating reactor is affected by external forces due to ocean conditions. These external forces can cause additional accelerations and affect each system and equipment of the marine reactor. Therefore, in designing a marine reactor and evaluating its performance and stability, a thermal hydraulic safety analysis code is necessary to consider the thermal hydrodynamic effects of ship motion. MARS, which is a reactor system analysis code, includes a dynamic motion model that can simulate the thermal-hydraulic phenomena under three-dimensional motion by calculating the body force term included in the momentum equation. In this study, it was verified that the dynamic motion model can simulate fluid motion with reasonable accuracy using conceptual problems. In addition, two modifications were made to the dynamic motion model; first, a user-supplied table to simulate a realistic ship motion was implemented, and second, the flow regime map determination algorithm was improved by calculating the volume inclination information at every time step if the dynamic motion model was activated. With these modifications, MARS could simulate the thermal-hydraulic phenomena under ocean motion more realistically.
Keywords
Dynamic motion model; System analysis code; Marine reactor; Ocean condition; Verification;
Citations & Related Records
Times Cited By KSCI : 1  (Citation Analysis)
연도 인용수 순위
1 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
2 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
3 B.H. Yan, L. Yu, Y.Q. Li, Research on operational characteristics of passive residual heat removal system under rolling motion, Nucl. Eng. Des. 239 (2009) 2302-2310.   DOI
4 J.S. Hwang, Experiment on Critical Heat Flux under Rolling Condition for TAPINS-M Code Development, Doctoral thesis, Seoul National University, Dept. Nuclear Engineering, 2013.
5 Y.G. Lee, G.C. Park, TAPINS: a thermal-hydraulic system code for transient analysis of a fully-passive integral PWR, Nucl. Eng. Technol. 45 (2013) 439-458.   DOI
6 E.V. Lewis, The Motion of Ships in Waves. Principles of Naval Architecture New York, 1967.
7 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
8 RELAP/MOD3 Code Manual Volume I: Code Structure, System Models, and Solution Methods, U.S. Nuclear Regulatory Commission, NUREG/CR-5535, 1998.
9 J.J. Jeong, S.W. Lee, J.Y. Cho, B.D. Chung, A coupled analysis of system thermalhydraulics and three-dimensional reactor kinetics for a 12-finger control element assembly drop event in a PWR plant, Ann. Nucl. Energy 37 (2010) 1580-1587.   DOI
10 J.S. Kim, M.Il Roh, S.H. Ham, A method for intermediate flooding and sinking simulation of a damaged floater in time domain, J. Comput. Des. Eng. 4 (2017) 1-13.   DOI
11 H. Murata, K. Sawada, M. Kobayashi, Natural circulation characteristics of a marine reactor in rolling motion and heat transfer in the core, Nucl. Eng. Des. 215 (2002) 69-85.   DOI
12 G.L. Mesina, D.L. Aumiller, F.X. Buschman, M.R. Kyle, Modeling moving systems with RELAP5-3D, Nucl. Sci. Eng. 182 (2016) 83-95.   DOI
13 T. Ishida, I. Tomiai, Development of Analysis Code for Thermal Hydrodynamics of Marine Reactor under Multi-Dimensional Ship Motions, RETRAN-02/GRAV, JAERI-M-91-226, Japan, 1992.
14 J.H. Kim, Development of RETRAN-03 Code for Thermal-Hydraulic Analysis of Nuclear Reactor under Multi-Dimensional Motions, Master Thesis, Seoul National University, Dept. Nuclear Engineering, 1996 (In Korean).
15 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
16 F.M. White, Fluid Mechanics, 7th Edition, McGraw Hill, New York, 2011.
17 D.T. Greenwood, Principles of Dynamics, Prentice-hall, Inc., Englewood Cliffs, New Jersey, 1987.