Researching | Neutronics-thermal-hydraulics-material coupling study of lead-bismuth cooled reactor single rod based on oxidative corrosion characteristics

NUCLEAR TECHNIQUES, Volume. 47, Issue 11, 110604(2024)

Neutronics-thermal-hydraulics-material coupling study of lead-bismuth cooled reactor single rod based on oxidative corrosion characteristics

Xu JI^1,2, Xiang CHAI^1,2, Lefu ZHANG^1,2, and Xiaojing LIU^1,2、*

Author Affiliations

¹School of Mechanical Engineering, Shanghai Jiao Tong University, Shanghai 200240, China

²Shanghai Digital Nuclear Reactor Technology Intergration Innovation Center, Shanghai 200240, China

show less

Abstract Get PDF(in Chinese)

Figures&Tables (11)

References (25)

Paper Information

References(25)

[1] Mylonakis A G, Varvayanni M, Catsaros N et al. Multi-physics and multi-scale methods used in nuclear reactor analysis[J]. Annals of Nuclear Energy, 72, 104-119(2014).

[2] Zhang J S, Li N. Review of the studies on fundamental issues in LBE corrosion[J]. Journal of Nuclear Materials, 373, 351-377(2008).

[3] Bonifetto R, Dulla S, Ravetto P et al. A full-core coupled neutronic/thermal-hydraulic code for the modeling of lead-cooled nuclear fast reactors[J]. Nuclear Engineering and Design, 261, 85-94(2013).

[4] Shen Y O, Peng S N, Yan M Y et al. Analytical study of heat transfer for liquid metals in a turbulent tube flow[J]. Nuclear Engineering and Design, 373, 111030(2021).

[5] Feng W P, Zhang X, Cao L K et al. Development of oxygen/corrosion product mass transfer model and oxidation-corrosion model in the lead-alloy cooled reactor core[J]. Corrosion Science, 190, 109708(2021).

[6] Luo X, Wang C, Zou Z R et al. Development and application of a multi-physics and multi-scale coupling program for lead-cooled fast reactor[J]. Nuclear Science and Techniques, 33, 18(2022).

[7] Lu D S, Wang C, Wang C L et al. Numerical simulation of corrosion phenomena in oxygen-controlled environment for a horizontal lead-bismuth reactor core[J]. Journal of Nuclear Materials, 574, 154195(2023).

[8] Gaston D, Newman C, Hansen G et al. MOOSE: a parallel computational framework for coupled systems of nonlinear equations[J]. Nuclear Engineering and Design, 239, 1768-1778(2009).

[9] Lindsay A, Ridley G, Rykhlevskii A et al. Introduction to Moltres: an application for simulation of Molten Salt Reactors[J]. Annals of Nuclear Energy, 114, 530-540(2018).

[10] Park S M, Huff K D. Multiphysics benchmark results from moltres[J]. Transactions of the American Nuclear Society, 124, 536-539(2021).

[11] Park S M, Munk M. Verification of moltres for multiphysics simulations of fast-spectrum molten salt reactors[J]. Annals of Nuclear Energy, 173, 109111(2022).

[12] Peterson J W, Lindsay A D, Kong F D. Overview of the incompressible Navier-Stokes simulation capabilities in the MOOSE framework[J]. Advances in Engineering Software, 119, 68-92(2018).

[13] Zhang J S. Long-term behaviors of oxide layer in liquid lead-bismuth eutectic (LBE), Part I: model development and validation[J]. Oxidation of Metals, 80, 669-685(2013).

[14] Zhang J S. Long-term behaviors of oxide layer in liquid lead-bismuth eutectic (LBE), Part II: model applications[J]. Oxidation of Metals, 81, 597-615(2014).

[15] Steiner H, Schroer C, Voss Z et al. Modeling of oxidation of structural materials in LBE systems[J]. Journal of Nuclear Materials, 374, 211-219(2008).

[16] Martinelli L, Balbaud-Célérier F, Terlain A et al. Oxidation mechanism of a Fe-9Cr-1Mo steel by liquid Pb-Bi eutectic alloy (Part I)[J]. Corrosion Science, 50, 2523-2536(2008).

[17] Martinelli L, Balbaud-Célérier F, Terlain A et al. Oxidation mechanism of an Fe-9Cr-1Mo steel by liquid Pb-Bi eutectic alloy at 470 ℃ (Part II)[J]. Corrosion Science, 50, 2537-2548(2008).

[18] Martinelli L, Balbaud-Célérier F, Terlain A et al. Oxidation mechanism of a Fe-9Cr-1Mo steel by liquid Pb-Bi eutectic alloy (Part III)[J]. Corrosion Science, 50, 2549-2559(2008).

[19] Martinelli L, Balbaud-Célérier F. Modelling of the oxide scale formation on Fe-Cr steel during exposure in liquid lead-bismuth eutectic in the 450–600 ℃ temperature range[J]. Materials and Corrosion, 62, 531-542(2011).

[20] Weisenburger A, Schroer C, Jianu A et al. Long term corrosion on T91 and AISI1 316L steel in flowing lead alloy and corrosion protection barrier development: experiments and models[J]. Journal of Nuclear Materials, 415, 260-269(2011).

[21] Weisenburger A, Heinzel A, Müller G et al. T91 cladding tubes with and without modified FeCrAlY coatings exposed in LBE at different flow, stress and temperature conditions[J]. Journal of Nuclear Materials, 376, 274-281(2008).

[22] Tsisar V, Schroer C, Wedemeyer O et al. Characterization of corrosion phenomena and kinetics on T91 ferritic/martensitic steel exposed at 450 and 550 ℃ to flowing Pb-Bi eutectic with 10-7 mass% dissolved oxygen[J]. Journal of Nuclear Materials, 494, 422-438(2017).

[23] YANG Dongmei. Research and application of nuclear thermal coupling in small lead-cooled fast reactor core[D](2020).

[25] Carbajo J J. Thermophysical properties of MOX and UO2 fuels including the effects of irradiation[R](2011).

[26] Samsonov G V[M]. The oxide handbook(1973).

Tools

Get Citation

Copy Citation Text

Xu JI, Xiang CHAI, Lefu ZHANG, Xiaojing LIU. Neutronics-thermal-hydraulics-material coupling study of lead-bismuth cooled reactor single rod based on oxidative corrosion characteristics[J]. NUCLEAR TECHNIQUES, 2024, 47(11): 110604

Download Citation

EndNote(RIS)BibTex Plain Text

Set citation alerts for article

Save article for my favorites

Paper Information

Category: NUCLEAR ENERGY SCIENCE AND ENGINEERING

Received: Nov. 29, 2023

Accepted: --

Published Online: Jan. 2, 2025

The Author Email: LIU Xiaojing (LIUXiaojing)

DOI:10.11889/j.0253-3219.2024.hjs.47.110604

Topics

laser devices and laser physics

Lasers and Laser Optics

laser manufacturing

Instrumentation, Measurement and Metrology