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2023•E3S Web of ConferencesOpen access

Study of burnup process in the VVER-1200 reactor with plutonium refueling options

Dilmurod Tuymurodov, Abror Tuymuradov, Satimboy Palvanov, A.Kh. Ramazonov, Sindorjon Ashurov, M. I. Mamayusupova, Tursunali Khamidov

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Abstract

This paper aims to investigate and compare the burnup processes of the VVER-1200 reactor fueled with reactor-grade and weapon-grade plutonium mixed with depleted uranium (MOX) through simulation with the GETERA code. The burnup calculation was performed using a unit fuel cell model, taking into account the center hole of the fuel pellet and the gas gap between the fuel and the cladding. The number of reloads for all cases was calculated. The infinite multiplication factor versus burnup graphs, as well as the behaviors of isotopes under all conditions, have been obtained and studied. The graphs of the infinite multiplication factor versus burnup and the behaviors of isotopes for all cases were obtained and analyzed. The results showed closing the VVER-1200 fuel cycle can be achieved by using MOX fuel.

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What this paper is about

This paper aims to investigate and compare the burnup processes of the VVER-1200 reactor fueled with reactor-grade and weapon-grade plutonium mixed with depleted uranium (MOX) through simulation with the GETERA code. The burnup calculation was performed using a unit fuel cell model, taking into account the center hole of the fuel pellet and the gas gap between the fuel and the cladding. The number of reloads for all cases was calculated. The infinite multiplication factor versus burnup graphs, as well as the behaviors of isotopes under all conditions, have been obtained and studied. The graphs of the infinite multiplication factor versus burnup and the behaviors of isotopes for all cases were obtained and analyzed. The results showed closing the VVER-1200 fuel cycle can be achieved by using MOX fuel.

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Available abstract

This paper aims to investigate and compare the burnup processes of the VVER-1200 reactor fueled with reactor-grade and weapon-grade plutonium mixed with depleted uranium (MOX) through simulation with the GETERA code. The burnup calculation was performed using a unit fuel cell model, taking into account the center hole of the fuel pellet and the gas gap between the fuel and the cladding. The number of reloads for all cases was calculated. The infinite multiplication factor versus burnup graphs, as well as the behaviors of isotopes under all conditions, have been obtained and studied. The graphs of the infinite multiplication factor versus burnup and the behaviors of isotopes for all cases were obtained and analyzed. The results showed closing the VVER-1200 fuel cycle can be achieved by using MOX fuel.

Key concepts: Burnup, VVER, Nuclear engineering, Plutonium, MOX fuel, Spent nuclear fuel, Fissile material, Environmental science

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