journal article·2021-10-18Open access

Prediction of Dissolved Impurities and Movement of Oxide Particles in the Primary Circuit of LBE Fast Reactor

Jiewei Wu, Rongjun Wu, Yuqing Wang, Jianbo He, Chen Hu, Xian Zeng, Muyi Ni

Coatings· Volume 11· Issue 10

Abstract

To better understand the corrosion and corrosion products behavior in the primary circuit of lead-bismuth eutectic (LBE) coolant reactor, the concentration distribution of soluble impurities and the transport of solid particles are investigated through the finite-element method. An axisymmetric model of the primary circuit of an LBE reactor was constructed to accelerate the calculation of the thermal hydraulic filed of the circuit. The saturation concentration of solute Fe, Cr and Ni in LBE coolant are identified through the equilibrium of their oxides and PbO, and the very different saturation concentrations of Fe/Cr/Ni in LBE will lead to significant element-selective corrosion. The migration of solid oxide particles in the primary circuit is also investigated by the Euler–Lagrange tracing model. The simulation shows that driving force for the movement of particles >100 μm is buoyancy, which lets particles float on a free surface, while particles <10 μm tend to suspend in coolant. However, the behavior of particles also depends on the formation position, the particles formed above the core have a high possibility of re-entering in the core.
Source: crossref · Quality: baseline

Research context

OpenAlex topics: Nuclear reactor physics and engineering · Nuclear Materials and Properties · Cyclone Separators and Fluid Dynamics

SciVX discovery tags are terminology-based. OpenAlex topics are source-provided classifications.

Affiliations

Sino-French Institute of Nuclear Engineering and Technology, Sun Yat-Sen University, Zhuhai 510080, China

The Wuhan Second Boat Institution, Wuhan 430200, China

China Nuclear Power Technology Research Institute Co., Ltd., Shenzhen 518000, China

Funding

National Defense Pre-Research Foundation of China · Fundamental Science on Nuclear Wastes and Environmental 294 Safety Laboratory

References (24)

Show source-provided references
1. Review of the studies on fundamental issues in LBE corrosion10.1016/j.jnucmat.2007.06.019 ↗
2. An overview of corrosion issues for the design and operation of high-temperature lead-and lead-bismuth-cooled reactor systems10.13182/NT04-A3540 ↗
3. Gromov, B., Orlov, Y., Martynov, P., and Gulevsky, V. (1998, January 5–9). The problems of technology of the heavy liquid metal coolants. Proceedings of the Heavy Liquid Metal Coolants in Nuclear Technology Conference, Obninsk, Russia.
4. Oxidation of steel T91 in flowing lead–bismuth eutectic (LBE) at 550° C10.1016/j.jnucmat.2006.05.009 ↗
5. Corrosion/precipitation in non-isothermal and multi-modular LBE loop systems10.1016/j.jnucmat.2004.01.013 ↗
6. Hydrodynamic problems of heavy liquid metal coolants technology in loop-type and mono-block-type reactor installations10.1016/j.nucengdes.2007.03.008 ↗
7. Numerical modeling of iron-based corrosion product oxides mass transport in the MYRRHA reactor during normal operation10.1016/j.nucengdes.2018.08.008 ↗
8. Oxidation behaviour of P122 and a 9Cr–2W ODS steel at 550 C in oxygen-containing flowing lead–bismuth eutectic10.1016/j.jnucmat.2009.10.019 ↗
9. Investigation on oxygen controlled liquid lead corrosion of surface treated steels10.1016/S0022-3115(99)00211-1 ↗
10. Active control of oxygen in molten lead–bismuth eutectic systems to prevent steel corrosion and coolant contamination10.1016/S0022-3115(01)00713-9 ↗
11. Structural materials for power plants with heavy liquid metals as coolants
12. Martynov, P., Askhadullin, R.S., Simakov, A., Chaban’, A.Y., and Legkikh, A.Y. (2009, January 12–16). Designing mass exchangers for control of oxygen content in Pb-Bi (Pb) coolants in various research facilities. Proceedings of the International Conference on Nuclear Engineering, Brussels, Belgium.10.1115/ICONE17-75506 ↗
13. Oxygen–iron interaction in liquid lead–bismuth eutectic alloy10.1039/C6CP01561A ↗
14. Models of liquid metal corrosion10.1016/j.jnucmat.2010.05.024 ↗
15. Problems of high-temperature liquid-metal corrosion of refractory metals and alloys
16. Heavy liquid metal coolant–lead–bismuth and lead–technology10.1023/B:ATEN.0000047678.35315.b6 ↗
17. Koloszar, L. (2014, January 20–22). CFD simulation of the thermohydraulics of the MYRRHA reactor. Proceedings of the THINS 2014 International Workshop, Modena, Italy.
18. Saeidi, S. (2014). Study of MHD Corrosion and Transport of Corrosion Products of Ferritic/Martensitic Steels in the Flowing PbLi and Its Application to Fusion Blanket, University of California.
19. Multi-physics model development for Polonium transport behavior in Lead-cooled Fast Reactor
20. MyrrhaFoam: A CFD model for the study of the thermal hydraulic behavior of MYRRHA10.1016/j.nucengdes.2016.05.008 ↗
21. Fazio, C., Sobolev, V., Aerts, A., Gavrilov, S., Lambrinou, K., Schuurmans, P., Gessi, A., Agostini, P., Ciampichetti, A., and Martinelli, L. (2015). Handbook on Lead-Bismuth Eutectic Alloy and Lead Properties, Materials Compatibility, Thermal-Hydraulics and Technologies, Organisation for Economic Co-Operation and Development. [2015th ed.].
22. Crespo, L. (2007). Compatibility of structural materials with LBE and Pb: Standardization of data, corrosion mechanism and rate. Handbook on Lead–Bismuth Eutectic Alloy and Lead Properties, Material Compatibility, Thermal-Hydraulics and Technologies, Nuclear Energy Agency, Nuclear Science Committee.
23. Filtration purification of heavy liquid metal coolants from impurities
24. An investigation of particle trajectories in two-phase flow systems10.1017/S0022112072001806 ↗