Corrosion resistance of structural materials in boron-containing solutions

Belous, Vladimir; Gromova, A. I.; Shapovalov, É. T.; Gerasimov, V. V.

doi:10.1007/bf02153710

Cited by 2 publications

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“…As a result, the electron consumption ability of water and the rate of metal cation production rise, resulting in an increase in corrosion rate. [ 1 ] To avoid this, the lithium hydroxide (LiOH) is likewise incorporated to regulate the coolant pH, reducing the corrosion of component materials and the accumulation of sediment in the fuel cladding and pipeline. Therefore, the control and optimization of H 3 BO 3 and LiOH in primary hydrochemistry have always been of concern.…”

Section: Introductionmentioning

confidence: 99%

Atomic‐Scale Investigations of H₃BO₃and LiOH on Zr(0 0 0 1) Surface: A DFT Study

Ren

Suo

et al. 2023

Advcd Theory and Sims

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The boric acid (H 3 BO 3 ) and lithium hydroxide (LiOH) are routinely added to primary water as soluble neutron absorbers and pH regulating agents in the pressured water reactor nuclear power plant, respectively. Previous studies mostly focus on the service behavior of nuclear materials using experimental methods, whereas the microscopic mechanism of H 3 BO 3 and LiOH on Zr-based fuel cladding remains largely unclear. With the first principle approach of density functional theory (DFT), the geometric structure, Mulliken population, partial densities of states, and electron density difference are adopted to study the adsorption characteristics and binding strength of H 3 BO 3 and LiOH on Zr matrix. The results show that when H 3 BO 3 and LiOH react on the Zr matrix, there is formation of hybrid peaks and new bonds between surface molecules and the matrix. Meanwhile, the vertical molecule has a substantial impact on electron movement between adsorbs and the matrix. The interaction energy between two molecules and the Zr surface in turn is LiOH > H 3 BO 3 , demonstrating that LiOH has the most influence on the fuel cladding in the primary circuit.

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Section: Introductionmentioning

confidence: 99%

Atomic‐Scale Investigations of H₃BO₃and LiOH on Zr(0 0 0 1) Surface: A DFT Study

Ren

Suo

et al. 2023

Advcd Theory and Sims

View full text Add to dashboard Cite

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10. Release of alloying constituents of stainless steel in SGHWR calandria environment

Jarvis¹

1978

Water Chemistry of Nuclear Reactor Systems

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Corrosion resistance of structural materials in boron-containing solutions

Cited by 2 publications

References 1 publication

Atomic‐Scale Investigations of H₃BO₃and LiOH on Zr(0 0 0 1) Surface: A DFT Study

Atomic‐Scale Investigations of H₃BO₃and LiOH on Zr(0 0 0 1) Surface: A DFT Study

10. Release of alloying constituents of stainless steel in SGHWR calandria environment

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Corrosion resistance of structural materials in boron-containing solutions

Cited by 2 publications

References 1 publication

Atomic‐Scale Investigations of H3BO3and LiOH on Zr(0 0 0 1) Surface: A DFT Study

Atomic‐Scale Investigations of H3BO3and LiOH on Zr(0 0 0 1) Surface: A DFT Study

10. Release of alloying constituents of stainless steel in SGHWR calandria environment

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Atomic‐Scale Investigations of H₃BO₃and LiOH on Zr(0 0 0 1) Surface: A DFT Study

Atomic‐Scale Investigations of H₃BO₃and LiOH on Zr(0 0 0 1) Surface: A DFT Study