Principles of alloying a novel radiation-resistant austenitic steel for the VVER-1200 reactor internals guaranteeing their safe operation for at least 60 years

Kursevich, I. P.; Karzov, G. P.; Марголин, Б. З.; Sorokin, A. A.; Teplukhina, I. V.

doi:10.1134/s2075113313060099

Cited by 5 publications

(9 citation statements)

References 11 publications

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“…In the case of function ( 6), according to [5], it is necessary to change the values of the corresponding parameters to switch from the irradiation conditions of a fast reactor to the conditions in a thermal neutron reactor. However, it is stated in [10] that this is unnecessary for 18Cr10NiTi steel. For function ( 7), nothing needs to be changed, and you need to insert the variables of interest, irradiation temperature, dose, and dose rate [6,11].…”

Section: Discussionmentioning

confidence: 99%

“…Nevertheless, the authors of [5] use the power law of the dose dependence of swelling. For this purpose, they summarized available proprietary and literature experimental data for dose rates in the interval from 1.3•10 -7 to 8•10 -7 dpa/s and proposed the following function to describe the swelling of steel AISI 304 [10],…”

Section: Empirical Functions Of Swellingmentioning

confidence: 99%

“…( 5) at dose rates in the interval from 3•10 -7 to 6•10 -7 dpa/s and changed to c = 1.035•10 -2 , r = 1.5•10 -4 at dose rates in the interval from 0.6•10 -8 to 8•10 -8 dpa/s according to the paper [5]. It is proposed to use c = 1.035•10 -2 , r = 1.825•10 -4 at dose rates both (3…6)•10 -7 dpa/s, and (0.7…8)•10 -8 dpa/s according to the paper [10].…”

Section: Empirical Functions Of Swellingmentioning

confidence: 99%

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SWELLING PREDICTION OF AISI 304 AND 18Cr10NiTi AUSTENITIC STAINLESS STEELS USING VARIOUS EMPIRICAL FUNCTIONS

Kalchenko¹,

Lazarev²

2022

Problems of Atomic Science and Technology

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A review of the known empirical dependences of austenitic steel swelling on in-reactor environments is carried out. The performance of empirical functions is compared in application to the conditions of thermal neutron reactor internals. Comparison with experimental data is made, and the influence of statistical errors of reactor data is discussed. Finally, the applicability of the empirical functions in the space of external parameters, precisely temperature, dose, and dose rate, is investigated.

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Section: Discussionmentioning

confidence: 99%

Section: Empirical Functions Of Swellingmentioning

confidence: 99%

Section: Empirical Functions Of Swellingmentioning

confidence: 99%

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SWELLING PREDICTION OF AISI 304 AND 18Cr10NiTi AUSTENITIC STAINLESS STEELS USING VARIOUS EMPIRICAL FUNCTIONS

Kalchenko¹,

Lazarev²

2022

Problems of Atomic Science and Technology

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“…В качестве материалов ВКУ применяются аустенитные коррозионностойкие стали типа 08Х18Н10Т, в которых содержится около 10 масс.% никеля. Особенностью дан ных сталей является склонность к радиационному распуханию за счет образования пористости в условиях эксплуатации элементов ВКУ, что в итоге может приводить к недопустимому снижению трещиностойкости и прочностных характеристик [1,2].…”

Section: Introductionunclassified

The Role of Nickel in Forming a Structure Providing Increased Service Properties of Reactor Structural Materials

Kuleshova

Fedotov

Stepanov

et al. 2022

YadEn

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“…Austenitic steels of Cr18Ni9 type tending to the formation of alpha-phase caused by radiation deformation (Kursevich et al 2012) are used as the materials of elements of fast and thermal nuclear reactor internals. A series of radiation induced processes resulting in the radiation swelling and transformations of phase composition of steels which causes degradation of physical and mechanical properties develop under the effects of reactor irradiation (Margolin et al 2009) thus restricting the reactor ultimate life.…”

Section: Introductionmentioning

confidence: 99%

A study into the structure and physical properties of the Cr18Ni9-grade steel following long-term irradiation as part of the BN-600 reactor internals

Portnykh¹,

Козлов²,

Panchenko³

et al. 2020

NUCET

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The microstructures and physical properties of the austenitic Cr18Ni9-grade steel after 22 and 33 years of operation as part of the reactor internals were tested for assessing the conditions of the BN-600 reactor non-replaceable components (internals) and the potential of their subsequent use in predicting the reactor ultimate life. The paper presents histograms of the porosity distribution depending on the void size, in samples taken from portions that were subjected to neutron irradiation with displacement rates ranging from 1.0×10–9 to 4.3×10–8 dpa/s at temperatures from 370 to 440 °C. The elasticity characteristics were measured by resonance-type ultrasonic technique for the samples taken from the same portions of material. It was demonstrated that swelling calculated using the histograms of the porosity distribution depending on the void size has the maximum value at ~415 °C and after 33 years of irradiation reaches values of ~3%. Long-term variations of Young’s modulus demonstrate non-monotonous dependence on the damage dose. The maximum relative variation of Young’s modulus after 22 and 33 years of operation does not exceed 2% and 6%, respectively, of the values corresponding to the initial state. It was shown that along with the irradiation-induced swelling the changes in the physical properties are also affected in the process of irradiation by other structural changes and, in particular, by the formation of secondary phases. As shown by the results of the studies, operation of the BN-600 reactor internals made of Cr18Ni9-grade steel can be extended beyond 33 years of service. The comparison of the results obtained for the material after 22 and 33 years of operation contains information required for describing subsequent changes of the structure and properties of the Cr18Ni9 internals. The obtained results can be used for forecasting the reactor ultimate life within the framework of existing and developed models.

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Principles of alloying a novel radiation-resistant austenitic steel for the VVER-1200 reactor internals guaranteeing their safe operation for at least 60 years

Cited by 5 publications

References 11 publications

SWELLING PREDICTION OF AISI 304 AND 18Cr10NiTi AUSTENITIC STAINLESS STEELS USING VARIOUS EMPIRICAL FUNCTIONS

SWELLING PREDICTION OF AISI 304 AND 18Cr10NiTi AUSTENITIC STAINLESS STEELS USING VARIOUS EMPIRICAL FUNCTIONS

The Role of Nickel in Forming a Structure Providing Increased Service Properties of Reactor Structural Materials

A study into the structure and physical properties of the Cr18Ni9-grade steel following long-term irradiation as part of the BN-600 reactor internals

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