Corrosion of Steels in Lead-Bismuth Flow

Kondo, Masatoshi; Takahashi, Minoru; Sawada, Naoki; Hata, Koji

doi:10.1080/18811248.2006.9711073

Cited by 43 publications

(13 citation statements)

References 16 publications

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“…The coolant velocity of LBE is limited to less than 2 m/second due to corrosion and erosion concerns of primary loop pipes. The inlet in‐core coolant temperatures are chosen accordingly to the material properties of martensitic steels, which can be used in contact with LBE if the operating temperature is not beyond 550°C . The size of the helium gap between the fuel pellet and cladding is chosen accordingly to the Korea Advanced Institute of Science and Technology (KAIST) micromodular reactor (MMR) design documentation to allow for higher smear density and to accommodate for the irradiation swelling of UN fuel types.…”

Section: The Design Strategy Of the Conceptual Corementioning

confidence: 99%

Core design of long‐cycle small modular lead‐cooled fast reactor

et al. 2018

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Summary A core design of small modular liquid‐metal fast reactor (SMLFR) cooled by lead‐bismuth eutectic (LBE) was developed for power reactors. The main design constraint on this reactor is a size constraint: The core needs to be small enough so that (1) it can be transported in a spent nuclear fuel (SNF) cask to meet the electricity demands in remote areas and off‐grid locations or so that (2) it can be used as a power source on board of nuclear icebreaker ships. To satisfy this design requirement, the active core of the reactor is 1 m in height and 1.45 m in diameter. The reactor is fueled with natural and 13.86% low‐enriched uranium nitride (UN), as determined through an optimization study. The reactor was designed to achieve a thermal power of 37.5 MW with an assumption of 40% thermal efficiency by employing an advanced energy conversion system based on supercritical carbon dioxide (S‐CO2) as working fluid, in which the Brayton cycle can achieve higher conversion efficiencies and lower costs compared to the Rankine cycle. The outer region of the core with low‐enriched uranium (LEU) performs the function of core ignition. The center region plays the role of a breeding blanket to increase the core lifetime for long cycle operation. The core working fluid inlet and outlet temperatures are 300°C and 422°C, respectively. The primary coolant circulation is driven by an electromagnetic pump. Core performance characteristics were analyzed for isotopic inventory, criticality, radial and axial power profiles, shutdown margins (SDM), reactivity feedback coefficients, and integral reactivity parameters of the quasi‐static reactivity balance. It is confirmed through depletion calculations with the fast reactor analysis code system Argonne Reactor Computation (ARC) that the designed reactor can be operated for 30 years without refueling. Preliminary thermal‐hydraulic analysis at normal operation is also performed and confirms that the fuel and cladding temperatures are within normal operation range. The safety analysis performed with the ARC code system and the UNIST Monte Carlo code MCS shows that the conceptual core is favorable in terms of self‐controllability, which is the first step towards inherent safety.

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Section: The Design Strategy Of the Conceptual Corementioning

confidence: 99%

Core design of long‐cycle small modular lead‐cooled fast reactor

et al. 2018

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“…Corrosion experiment in flowing LBE was conducted for structural materials such as commercialized steels under the hot leg condition of 550°C [5]. Oxygen potential was adequately chosen so that oxide protection layers were formed on steel surfaces.…”

Section: Commercialized Steelsmentioning

confidence: 99%

Overview of recent studies related to lead-alloy-cooled fast reactors

Takahashi

Pramutadi

et al. 2012

AIP Conference Proceedings

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The recent progress of the studies related to LFRs are summarized. The compatibility of materials with lead alloys has been clarified under steady and transient temperature conditions. Higher Cr content, Si and Al addition and Al-Fe alloy-coating improved corrosion resistance. The Al-Fe alloy-coated steel was not corroded even high temperature transient conditions. The ceramics of SiC and and Si 3 N 4 are expected to be used as cladding material for high temperature LFR. For the consideration of mass transport, the diffusion coefficient of Ni could be measured using Capillary methods. A new bubble visualization method in LBE with gamma-ray radiography was developed. The thermal interaction of LBE and lead droplets with sub-cooled water, and the fragmentation of droplets were investigated, and the visualization of volatile liquid in high temperature liquid were achieved.

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“…Poor corrosion resistance of most commercial Ni-rich high strength steels to chemical attack by lead (nickel is dissolved in lead) [10,11]; • Resistance to creep deformation, which is activated by the inner service pressure (10 bar) and the high operating temperatures (T > 800 • C) that can be reached, combined with the stresses due to the high specific weight of the fluid itself [12,13].…”

Section: Introductionmentioning

confidence: 99%

Materials for High Temperature Liquid Lead Storage for Concentrated Solar Power (CSP) Air Tower Systems

et al. 2021

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Today the technical limit for solar towers is represented by the temperature that can be reached with current accumulation and exchange fluids (molten salts are generally adopted and the max temperatures are generally below 600 °C), even if other solutions have been suggested that reach 800 °C. An innovative solution based on liquid lead has been proposed in an ongoing experimental project named Nextower. The Nextower project aims to improve current technologies of the solar sector by transferring experience, originally consolidated in the field of nuclear plants, to accumulate heat at higher temperatures (T = 850–900 °C) through the use of liquid lead heat exchangers. The adoption of molten lead as a heat exchange fluid poses important criticalities of both corrosion and creep resistance, due to the temperatures and structural stresses reached during service. Liquid lead corrosion issues and solutions in addition to creep-resistant material selection are discussed. The experimental activities focused on technical solutions adopted to overcome these problems in terms of the selected materials and technologies. Corrosion laboratory tests have been designed in order to verify if structural 800H steel coated with 6 mm of FeCrAl alloy layers are able to resist the liquid lead attack up to 900 °C and for 1000 h or more. The metallographic results were obtained by mean of scanning electron microscopy with an energy dispersive microprobe confirm that the 800H steel shows no sign of corrosion after the completion of the tests.

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Corrosion of Steels in Lead-Bismuth Flow

Cited by 43 publications

References 16 publications

Core design of long‐cycle small modular lead‐cooled fast reactor

Core design of long‐cycle small modular lead‐cooled fast reactor

Overview of recent studies related to lead-alloy-cooled fast reactors

Materials for High Temperature Liquid Lead Storage for Concentrated Solar Power (CSP) Air Tower Systems

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