Study of construction materials for a lead-cooled reactor

Bozin, S. N.; Rodchenkov, B. S.; Kashtanov, A. D.; Markov, V. G.; Yakovlev, V. A.; Schenkova, Izabella; Ivanov, Yu. A.; Ioltukhovskiy, A.G.; Leont’eva-Smirnova, M. V.

doi:10.1007/s10512-013-9639-5

Cited by 3 publications

(2 citation statements)

References 2 publications

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“…The other experimental study was about the 10Kh15N9S3B1 (EP-302) austenitic steel with fcc structure for the elements of the main equipment, which operated in contact with lead coolant to a maximum temperature 550 °C [4]. Several steels, for example, T91 and EP-823, were also studied by exposing them to either static or flowing liquid lead-bismuth eutectic under various exposure conditions about 500 °C to 550 °C.…”

Section: Introductionmentioning

confidence: 99%

Molecular dynamics simulation of corrosion and its inhibition: comparison of structural stability of Fe/FeNi/FeNiCr/FeNiCrTi steels under high-temperature liquid lead

Arkundato¹,

Syarifah²,

Shafi'i³

et al. 2022

Eureka: PE

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The liquid lead used in fast nuclear reactor has been known to be able to cause a significant damage to the steels. Therefore, finding new materials with high corrosion resistance is the goal of much research current days. Likewise, developing a way to prevent corrosion is also the goal of designers of nuclear reactors. In the present study, we studied materials: Fe, FeNi, FeNiCr, and FeNiCrTi (a type of SS 316L austenite steel), comparing their structural stability when interacted with molten liquid lead at 750 °C. The performance of each steel is compared under high-temperature molten lead coolant, checking the structure's stability to see the material resistance to corrosion attack of liquid lead. The corrosion can also be seen from the data of iron diffusion coefficient. The larger of the iron diffusion coefficient can be associated with larger corrosion because there is a high solubility of iron atoms from the steel surface to the molten lead. The popular way to prevent more corrosion is by injecting oxygen into the lead coolant. This current work uses the molecular dynamics method to simulate the corrosion and inhibition phenomena. The research aims to compare the performance of Fe, FeNi, FeNiCr, and FeNiCrTi under liquid lead at a temperature of 750. The diffusion coefficient of iron of material will be calculated to describe quantitatively the corrosion level of those structural materials and the corrosion inhibition by oxygen injection. The study has produced important results that adding Ni, Cr, Ti into a pure iron crystal to build alloy steel will make the material stronger, structurally compact, and more resistant to corrosion. For specific composition of steels, from weaker to stronger that resist from corrosion attack, it is possible to make ordering: Fe<<FeNi<FeNiCr<FeNiCrTi. The composition of FeNiCrTi steel in this work is Fe(75)Ni(10.57)Cr(14.05)Ti(0.40). The high corrosion of FeNiCrTi in the liquid lead is effectively reduced by injecting 0.0112 wt % oxygen into lead coolant as a limit value for maximum corrosion inhibition

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Section: Introductionmentioning

confidence: 99%

Molecular dynamics simulation of corrosion and its inhibition: comparison of structural stability of Fe/FeNi/FeNiCr/FeNiCrTi steels under high-temperature liquid lead

Arkundato¹,

Syarifah²,

Shafi'i³

et al. 2022

Eureka: PE

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“…As already noted, the EP-823 and EI-852 ferrite-martensite steels were developed specially for use in a reactor with lead-bismuth coolant [2,8,30]. The stability of the steel in lead is due to the elevated silicon content.…”

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confidence: 99%

Swelling and Radiation Creep of Ferrite-Martensite Steel Irradiated in the Bn-350 Reactor in a Wide Range of Temperature and Damaging Dose

et al. 2016

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The results of investigations of swelling and in-reactor creep of the ferrite-martensite class steels to damaging dose in the range 20-89 dpa are presented. The characteristics of radiation creep of three of the ferrite-martensite steels are close despite the differences of the chemical composition and heat-treatment. The relation B = 4.864·10 -2 + 1.45·10 -3 T describes the average modulus of radiation creep of the experimental steel in the interval 305-550°C.The transition of nuclear technologies to a new level and the development of next-generation reactor cores require structural materials for fuel elements and fuel assemblies that are capable of operating to damaging dose 150 dpa and higher. The development of such materials must be based on reliable data on the radiation damageability of prototype steel and research on the structural changes occurring under irradiation and the infl uence of these changes on the physical-mechanical properties. In this respect, ferrite-martensite class steels are the most promising materials for use in new nuclear plants. Several types of 12% chromium steel have been developed in our country for different purposes [1][2][3][4]. One of the most widely available steels is EP-450, which is used for fuel-assembly jackets and guide tubes of the safety-and-control system channels in BN-600 and -800 reactors [1, 5, 6]. The steels EI-852 and EP-823 were developed for facilities with lead-bismuth or lead coolant [2,7,8].The main advantages of ferrite-martensite steel are high resistance to vacancy swelling and low rate of radiation creep together with acceptable mechanical properties, which was shown in a post-irradiation investigation of this steel [9-13]. Nonetheless, there are not enough experimental data on radiation resistance; the greatest data defi ciency is observed for high damaging dose as well as low and high irradiation temperatures. Part of this data was obtained by irradiating the steel in BN-350. This reactor was widely used to irradiate samples of structural materials. A feature of this reactor was low sodium temperature at the core entry, which together with throttling of the assemblies or additional heating of the samples made it possible to conduct irradiation in a temperature range that is inaccessible for other reactors.Material-research assemblies irradiated in BN-350 were investigated in the hot laboratory at the FEI over a period of many years. In the present article, we present the results of investigations of swelling and radiation creep of irradiated

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Review of phase equilibria in the Pb-Bi-Fe-Cr-Ni-U-N system – Basis for a “heavy liquid metal coolant – Fuel cladding steel – Nitride fuel” interactions

Timchuk,

Kurguzkina,

Shuvaeva

et al. 2024

Journal of Nuclear Materials

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Study of construction materials for a lead-cooled reactor

Cited by 3 publications

References 2 publications

Molecular dynamics simulation of corrosion and its inhibition: comparison of structural stability of Fe/FeNi/FeNiCr/FeNiCrTi steels under high-temperature liquid lead

Molecular dynamics simulation of corrosion and its inhibition: comparison of structural stability of Fe/FeNi/FeNiCr/FeNiCrTi steels under high-temperature liquid lead

Swelling and Radiation Creep of Ferrite-Martensite Steel Irradiated in the Bn-350 Reactor in a Wide Range of Temperature and Damaging Dose

Review of phase equilibria in the Pb-Bi-Fe-Cr-Ni-U-N system – Basis for a “heavy liquid metal coolant – Fuel cladding steel – Nitride fuel” interactions

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