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http://dx.doi.org/10.1016/j.net.2020.07.030

Development of TREND dynamics code for molten salt reactors  

Yu, Wen (Shanghai Institute of Applied Physics, Chinese Academy of Sciences)
Ruan, Jian (Shanghai Institute of Applied Physics, Chinese Academy of Sciences)
He, Long (Shanghai Institute of Applied Physics, Chinese Academy of Sciences)
Kendrick, James (Department of Nuclear Engineering, University of California)
Zou, Yang (Shanghai Institute of Applied Physics, Chinese Academy of Sciences)
Xu, Hongjie (Shanghai Institute of Applied Physics, Chinese Academy of Sciences)
Publication Information
Nuclear Engineering and Technology / v.53, no.2, 2021 , pp. 455-465 More about this Journal
Abstract
The Molten Salt Reactor (MSR), one of the six advanced reactor types of the 4th generation nuclear energy systems, has many impressive features including economic advantages, inherent safety and nuclear non-proliferation. This paper introduces a system analysis code named TREND, which is developed and used for the steady and transient simulation of MSRs. The TREND code calculates the distributions of pressure, velocity and temperature of single-phase flows by solving the conservation equations of mass, momentum and energy, along with a fluid state equation. Heat structures coupled with the fluid dynamics model is sufficient to meet the demands of modeling MSR system-level thermal-hydraulics. The core power is based on the point reactor neutron kinetics model calculated by the typical Runge-Kutta method. An incremental PID controller is inserted to adjust the operation behaviors. The verification and validation of the TREND code have been carried out in two aspects: detailed code-to-code comparison with established thermal-hydraulic system codes such as RELAP5, and validation with the experimental data from MSRE and the CIET facility (the University of California, Berkeley's Compact Integral Effects Test facility).The results indicate that TREND can be used in analyzing the transient behaviors of MSRs and will be improved by validating with more experimental results with the support of SINAP.
Keywords
Molten salt reactor; Transient analysis; Code development; Verification and validation;
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  • Reference
1 S.J. Ball, T.W. Kerlin, Stability Analysis of the Molten Salt Reactor Experiment, Oak Ridge National Laboratory, 1965. ORNL-TM-1070.
2 J. Serp, M. Allibert, The molten salt reactor (MSR) in generation IV: overview and perspectives, Prog. Nucl. Energy 77 (2014) 308-319.   DOI
3 M. Delpech, S. Dulla, C. Garzenne, Benchmark of dynamic simulation tools for molten salt reactors, in: Proceedings of the International Conference GLOBAL, New Orleans, LA, 2003.
4 M.S. Greenwood, B.R. Betzler, et al., Demonstration of the advanced dynamic system modeling tool transform in a molten salt reactor application via a model of the molten salt hemonstration reactor, Nucl. Technol. 206 (2019) 1-27.
5 M.H. Jiang, H.J. Xu, Z.M. Dai, Advanced fission energy program-TMSR nuclear energy system, Bull. Chin. Acad. Sci. 3 (2012) 366-374 (In Chinese).
6 J. Krepel, U. Grundmann, et al., DYN3D-MSR spatial dynamics code for molten salt reactors, Ann. Nucl. Energy 34 (2007) 449-462.   DOI
7 M. Zanetti, A. Cammi, A. Luzzi, et al., Extension of the FAST code system for the modelling and simulation of MSR dynamics, in: International Congress on Advances in Nuclear Power Plants, May 03-06, 2015. Nice, France.
8 J. Ruan, Y. Zou, et al., Fluoride-salt cooled higlrtemperature reactor hardwareirrthe-loop simulation and preliminary test, Atom. Energy Sci. Technol. 52 (2018) 659-665 (In Chinese).
9 S. Patankar, Numerical Heat Transfer and Fluid Flow, first ed., Taylor & Francis, Oxford, 1980.
10 H. Francis Harlow, J.E. Welch, Numerical calculation of time-dependent viscous incompressible flow of fluid with free surface, Phys. Fluids 8 (1965) 2182.   DOI
11 R.C. Robertson, MSRE Design and Operations Report, Part I-Description of Reactor Design, Oak Ridge National Laboratory, 1965. ORNL-TM-278.
12 J. Krepel, U. Grundmann, et al., DYN1D-MSR dynamics code for molten salt reactors, Ann. Nucl. Energy 32 (2005) 1799-1824.   DOI
13 G.J. Auwerda, D. Lathouwers, Computational modeling of a molten salt Reactor, ResearchGate (2007). https://www.researchgate.net/publication/242184604.
14 N.E. Todreas, M.S. Kazimi, Nuclear Systems I Thermal Hydraulic Fundamentals, first ed., Hemisphere Publishing Corporation, New York, 1990.
15 C. Tripodo, A.D. Ronco, S. Lorenzi, Development of a control-oriented power plant simulator for the molten salt fast reactor, J. Nucl. Sci. Technol. 5 (2019) 13.
16 L. Kendrick Huddar, Application of frequency response methods in separate and integral effects tests for molten salt cooled and fueled reactors, Nucl. Eng. Des. 329 (2018) 3-11.   DOI
17 N. Zweibaum, J.E. Bickel, Design, Fabrication and Startup Testing of the Compact Integral Effects Test Facility in Support of Fluoride-Salt-Cooled, High Temperature Reactor Technology, in: International Topical Meeting on Nuclear Reactor Thermal Hydraulics, 2015. Chicago, August 30-September 4.
18 M.W. Rosenthal, P.R. Kasten, R.B. Briggs, Molten-salt reactors-pistory, states, and potential, Nucl. App. Technol. 8 (1970) 107-117.   DOI
19 C. Forsberg, The advanced high-temperature reactor: high-temperature fuel, liquid salt coolant, liquid-metal-reactor plant, Prog. Nucl. Energy 47 (2005) 32-43.   DOI
20 P.N. Haubenreich, Molten-salt Reactor Experiments, Oak Ridge National Laboratory, 1969. ORNL-4344.
21 B.E. Prince, J.R. Engel, S.J. Ball, Zero-power Physical Experiments on Molten-Salt Reactor Experiment, Oak Ridge National Laboratory, 1968. ORNL-4233.
22 J. Cai, X.B. Xia, Analysis on reactivity initiated transient from control rod failure events of a molten salt reactor, Nucl. Sci. Tech. 25 (2014) 78-82.   DOI
23 F. Allan Henry, Scott, Nuclear Reactor Analysis, first ed., John Wiley and Sons, New York, 1976.
24 F. Blanchon, T. Ha-Duong, J. Planchard, Numerical methods for solving the reactor kinetic equations, Prog. Nucl. Energy 22 (1988) 173-180.   DOI
25 E. Virgil Schrock, A revised ANS Standard for decay heat from fission products, Nucl. Technol. 46 (1979) 323-331.   DOI
26 K.J. Astrom, T. Hagglund, PID Controllers : Theory, Design and Tuning, first ed., Instrument Society of America, New York, 1995.
27 C.B. Shi, M.S. Cheng, G.M. Liu, Development and application of a system analysis code for liquid fueled molten salt reactors based on RELAP5 code, Nucl. Eng. Des. 305 (2016) 378-388.   DOI