Water chemistry

Guzonas, David

doi:10.1016/b978-0-08-102049-4.00004-0

Cited by 19 publications

(21 citation statements)

References 83 publications

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“…The SCWR, a class of high-temperature, high-pressure, water-cooled reactors, operates above the thermodynamic critical point of water—temperatures exceeding 373.95 °C and pressures above 22.1 megapascals (MPa) for light water (H 2 O) [ 11 ]. With core inlet and outlet temperatures set at 300 °C and 600 °C, respectively, and a nominal pressure of 25 MPa, the SCWR is an extremely energy-efficient system, achieving thermodynamic cycle efficiencies of over ~45%, significantly surpassing the ~28–32% efficiencies of current conventional pressurized water reactors [ 2 , 8 , 9 ]. This high efficiency offers substantial economic benefits through lower-cost electricity generation.…”

Section: Introductionmentioning

confidence: 99%

“…In this context, there is an urgent need to identify the optimal chemistry and materials under SCWR conditions [ 8 , 15 ]. This research is especially pivotal for the development of small modular SCWRs (SCW-SMRs), which are being considered for deployment in small remote communities and developing countries [ 7 ].…”

Section: Introductionmentioning

confidence: 99%

“…A major challenge in understanding the water chemistry of SCWRs and their SMR variants arises from limited knowledge about in-core radiolysis and the specific radiolytic species these systems produce. SCWRs operate under significantly higher temperatures and pressures—approximately 300–600 °C and 25 MPa—compared to current generation water-cooled reactors, which typically operate at temperatures of 250 to 330 °C and pressures around 10 MPa [ 8 , 15 , 16 ]. This distinct operating environment of SCWRs results in water chemistry that is markedly different from that of conventional water-cooled reactors.…”

Section: Introductionmentioning

confidence: 99%

“…This distinct operating environment of SCWRs results in water chemistry that is markedly different from that of conventional water-cooled reactors. Bridging this knowledge gap is crucial, as it directly impacts critical factors such as material corrosion and degradation, along with the transport of corrosion products [ 8 ]. Thus, addressing this gap is essential for ensuring the long-term viability and safety of SCWRs and SCW-SMRs.…”

Section: Introductionmentioning

confidence: 99%

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Supercritical Water: A Simulation Study to Unravel the Heterogeneity of Its Molecular Structures

Assomo,

Ebrahimi,

Jay-Gerin

et al. 2024

Molecules

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(1) Background: In the quest to accurately model the radiolysis of water in its supercritical state, a detailed understanding of water’s molecular structure, particularly how water molecules are arranged in this unique state, is essential. (2) Methods: We conducted molecular dynamics simulations using the SPC/E water model to investigate the molecular structures of supercritical water (SCW) over a wide temperature range, extending up to 800 °C. (3) Results: Our results show that at a constant pressure of 25 MPa, the average intermolecular distance around a reference water molecule remains remarkably stable at ~2.9 Å. This uniformity persists across a substantial temperature range, demonstrating the unique heterogeneous nature of SCW under these extreme conditions. Notably, the simulations also reveal intricate patterns within SCW, indicating the simultaneous presence of regions with high and low density. As temperatures increase, we observe a rise in the formation of molecular clusters, which are accompanied by a reduction in their average size. (4) Conclusions: These findings highlight the necessity of incorporating the molecular complexity of SCW into traditional track-structure chemistry models to improve predictions of SCW behavior under ionizing radiation. The study establishes a foundational reference for further exploration of the properties of supercritical water, particularly for its application in advanced nuclear technologies, including the next generation of water-cooled reactors and their small modular reactor variants that utilize SCW as a coolant.

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Section: Introductionmentioning

confidence: 99%

Section: Introductionmentioning

confidence: 99%

Section: Introductionmentioning

confidence: 99%

Section: Introductionmentioning

confidence: 99%

See 2 more Smart Citations

Supercritical Water: A Simulation Study to Unravel the Heterogeneity of Its Molecular Structures

Assomo,

Ebrahimi,

Jay-Gerin

et al. 2024

Molecules

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“…It has been shown [ 4 , 7 , 8 , 9 , 10 , 11 , 12 ] that austenitic stainless steels, F/M steels, titanium zirconium alloys, alumina-forming austenitic (AFA) stainless steel, and oxide dispersion-strengthened (ODS) steel can be used as candidate materials for different components of SWCR. All of these materials have a number of advantages and disadvantages.…”

Section: Introductionmentioning

confidence: 99%

Investigation of Stress Corrosion Cracking Resistance of Irradiated 12Cr Ferritic-Martensitic Stainless Steel in Supercritical Water Environment

et al. 2023

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The supercritical water-cooled reactors (SWCR) belong to Generation IV of reactors. These reactors have a number of advantages over currently operating WWERs and PWRs. These advantages include higher thermal efficiency, a more simplified unit design, and the possibility of incorporating it into a closed fuel cycle. It is therefore necessary to identify candidate materials for the SWCR and validate the safety and effectiveness of their use. 12Cr ferritic–martensitic (F/M) stainless steel is considered a candidate material for SWCR internals. Radiation embrittlement and corrosion cracking in the primary circuit coolant environment are the main mechanisms of F/M steels degradation during SWCR operation. Here, the stress corrosion cracking (SCC) in supercritical water at 390 and 550 °C of 12Cr F/M steel irradiated by neutrons to 12 dpa is investigated. Autoclave tests of specially designed disk specimens in supercritical water were performed. The tests were carried out under different constant load (CL), temperature 450 °C, and pressure in autoclave 25 MPa. The threshold stress, below which the SCC initiation of irradiated 12Cr F/M steel does not occur, was determined.

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Deposition of iron oxides in supercritical water reactor: A review

Wang

Khan

et al. 2021

J Inorg Organomet Polym

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Water chemistry

Cited by 19 publications

References 83 publications

Supercritical Water: A Simulation Study to Unravel the Heterogeneity of Its Molecular Structures

Supercritical Water: A Simulation Study to Unravel the Heterogeneity of Its Molecular Structures

Investigation of Stress Corrosion Cracking Resistance of Irradiated 12Cr Ferritic-Martensitic Stainless Steel in Supercritical Water Environment

Deposition of iron oxides in supercritical water reactor: A review

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