Relevant bibliographies by topics / VVER-1200; Serpent

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Academic literature on the topic 'VVER-1200; Serpent'

Author: Grafiati
Published: 5 June 2025
Last updated: 2 August 2025

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Journal articles on the topic "VVER-1200; Serpent"

1

Zhemzhurov, M. L., G. M. Zhmura, I. E. Rubin, et al. "Calculation researches for the formation of high-level and long-life medium-level radioactive waste of activation origin for the WWER-1200 reactor of Belarusian NPP." Proceedings of the National Academy of Sciences of Belarus, Physical-Technical Series 66, no. 3 (2021): 365–77. http://dx.doi.org/10.29235/1561-8358-2021-66-3-365-377.

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The study of the issue of constructing a disposal facility for high-activity radioactive waste in the Republic of Belarus is associated with an assessment of the volume of radioactive waste to be deeply disposed of, generated as a result of the activation of structural materials of the VVER-1200 reactor of the Belarusian NPP. This paper presents the results of computational studies of the formation of solid high-level radioactive waste (HLW) and long-lived intermediate level radioactive waste (ILW-LL) during neutron activation of materials adjacent to the core of the VVER-1200 reactor structur
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2

Pramanik, Md Masum Rana. "Effect of the burnable absorber on the efficiency of nuclear fuel cycle in VVER-1200 reactor." SciEn Conference Series: Engineering 1 (May 7, 2025): 81–85. https://doi.org/10.38032/scse.2025.1.15.

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The significant impacts of burnable absorbers (UO2+Gd2O3) on reactivity, neutron multiplication factor (Keff), burnup, neutron flux distribution, power peaking factor, as well as safety criterions of the VVER-1200 reactor are discussed in this paper. Fuel economics have improved, resulting in increased enrichment of fuel & the need for better neutron flux distribution as well as reactivity controls. In order to achieve these enhancements in neutron flux distribution, burnable absorbers must be incorporated into the fuel matrix. To compute the 3D (three-dimensional) model for VVER-1200 fuel
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Zhemzhurov, M. L., G. M. Zhmura, I. E. Rubin, et al. "Determination of volume of radioactive waste in activated VVER-1200 reactor structures." Proceedings of the National Academy of Sciences of Belarus. Physical-technical series 69, no. 1 (2024): 39–52. http://dx.doi.org/10.29235/1561-8358-2024-69-1-39-52.

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The results of calculation studies of the amount of solid high-level, intermediate-level, low-level, very lowlevel radioactive waste (HLW, ILW, LLW, VLLW, respectively) generated during neutron activation of structural materials adjacent to the core of the VVER-1200 reactor plant, depending on the time after the final stopping it. An assessment of the volumes of radioactive waste (RAW) of activation origin generated over 60 years of operation of a VVER-1200 type reactor was carried out on the basis of computational studies of the induced activity of structural and protective materials using re
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4

Kovalev, Nikita V., Alexander M. Prokoshin, Alexander S. Kudinov, and Vladimir A. Nevinitsa. "Use of remix spent mixed fuel plutonium in the BN-1200 reactor." Nuclear Energy and Technology 9, no. 2 (2023): 131–36. http://dx.doi.org/10.3897/nucet.9.107762.

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The VVER-1000 thermal neutron reactor can operate on mixed uranium-plutonium fuel with a content of reactor-grade plutonium up to 5% with a 100% loaded core. In this case, plutonium burns up to 56% of odd isotopes. The energy potential of such plutonium is very low, and its further use in thermal reactors is impractical. However, such plutonium can be used in fast neutron reactors. The paper presents the results of investigating the possibility for such isotopic plutonium composition to be used in the BN-1200 thermal neutron reactor and its value be increased for the plutonium recycle in the r
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Kovalev, Nikita V., Alexander M. Prokoshin, Alexander S. Kudinov, and Vladimir A. Nevinitsa. "Use of remix spent mixed fuel plutonium in the BN-1200 reactor." Nuclear Energy and Technology 9, no. (2) (2023): 131–36. https://doi.org/10.3897/nucet.9.107762.

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The VVER-1000 thermal neutron reactor can operate on mixed uranium-plutonium fuel with a content of reactor-grade plutonium up to 5% with a 100% loaded core. In this case, plutonium burns up to 56% of odd isotopes. The energy potential of such plutonium is very low, and its further use in thermal reactors is impractical. However, such plutonium can be used in fast neutron reactors. The paper presents the results of investigating the possibility for such isotopic plutonium composition to be used in the BN-1200 thermal neutron reactor and its value be increased for the plutonium recycle in the r
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6

Khrushchinsky, A. A., S. A. Kuten, and L. F. Babichev. "Calculation of DPA for the VVER-1200 Reactor Vessel." Interdisciplinary Journal Nonlinear Phenomena in Complex Systems 27, no. 2 (2024): 194–98. https://doi.org/10.5281/zenodo.12645503.

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Neutron irradiation damage is of the  most critical damagemechanisms in reactor vessel (RV) steel. Neutrons transfer theirkinetic energy to target atoms of RV steel that start to jumpcreating vacancies and interstitials known as Frenkel Pairs (FP).The FPs are responsible for formation of defected clusters andmicrostructural modifications. These effects deteriorate physicaland mechanical properties of the RV steels among  which results inlimiting the lifetime of reactor vessel. The most sensitivelocation in the RV related neutron irradiation damages is the areaadjacent to the middle o
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7

Zhemzhurov, M. L., G. M. Zhmura, I. E. Rubin, et al. "Predictive evaluation of changes in the volumes of radioactive waste to be deeply dispositioned in activated reactor structures in the process of their storage after the final shutdown of the Belarusian NPP power units." Proceedings of the National Academy of Sciences of Belarus, Physical-Technical Series 67, no. 3 (2022): 332–44. http://dx.doi.org/10.29235/1561-8358-2022-67-3-332-344.

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This paper presents the results of computational studies of the amount of solid high-level and long-lived intermediate level radioactive waste (HLW and ILW-LL) generated during neutron activation of structural materials adjacent to the core of the VVER-1200 reactor of the Belarusian NPP, depending on the time after the final shutdown of the reactor. The assessment of the volumes of HLW and ILW-LL of activation origin, formed over 60 years of operation of the VVER-1200 reactor, was carried out on the basis of computational studies of the induced activity of structural and shielding materials us
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8

Lavronenko, Aleksey V., Vyacheslav G. Savankov, Ruslan A. Vnukov, and Elena A. Chistozvonova. "Comparison of methods for calculating the neutronic characteristics of a VVER-1200 fuel assembly." Nuclear Energy and Technology 8, no. 3 (2022): 161–65. http://dx.doi.org/10.3897/nucet.8.93894.

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This article presents the results of neutronic calculations of a VVER-1200 fuel assembly carried out using the multi-purpose three-dimensional continuous-energy Monte Carlo particle transport code Serpent 2. The study compares neutronic characteristics during the fuel burnup process (1) with and (2) without fuel cooling. In the first option, the FA fuel campaign was simulated with 30-day cooling periods between reactor campaigns. The second option assumed simulating the FA fuel campaign without fuel cooling. In the course of the study, the authors determined the infinite neutron multiplication
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9

Lavronenko, Aleksey V., Vyacheslav G. Savankov, Ruslan A. Vnukov, and Elena A. Chistozvonova. "Comparison of methods for calculating the neutronic characteristics of a VVER-1200 fuel assembly." Nuclear Energy and Technology 8, no. (3) (2022): 161–65. https://doi.org/10.3897/nucet.8.93894.

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This article presents the results of neutronic calculations of a VVER-1200 fuel assembly carried out using the multi-purpose three-dimensional continuous-energy Monte Carlo particle transport code Serpent 2. The study compares neutronic characteristics during the fuel burnup process (1) with and (2) without fuel cooling. In the first option, the FA fuel campaign was simulated with 30-day cooling periods between reactor campaigns. The second option assumed simulating the FA fuel campaign without fuel cooling. In the course of the study, the authors determined the infinite neutron multiplication
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10

Hossain, Md Imtiaj, Yasmin Akter, Mehraz Zaman Fardin, and Abdus Sattar Mollah. "Neutronics and burnup analysis of VVER-1000 LEU and MOX assembly computational benchmark using OpenMC Code." Nuclear Energy and Technology 8, no. 1 (2022): 1–11. http://dx.doi.org/10.3897/nucet.8.78447.

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A handful of computational benchmarks that incorporate VVER-1000 assemblies having low enriched uranium (LEU) and the mixed oxide (MOX) fuel have been put forward by many experts across the world from the Nuclear Energy Agency. To study & scrutinize the characteristics of one of the VVER-1000 LEU & MOX assembly benchmarks in different states were considered. In this work, the VVER-1000 LEU and MOX Assembly computational-benchmark exercises are performed using the OpenMC software. The work was intended to test the preciseness of the OpenMC Monte Carlo code using nuclear data lib
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Conference papers on the topic "VVER-1200; Serpent"

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Anisur, Sk R., and D. Debashis. "INVESTIGATION OF HYDROGEN PRODUCTION IN ACCIDENT SCENARIOS OF VVER-1200 REACTOR COMPARING ZIRCONIUM-BASED CLADDING WITH ACCIDENT TOLERANT FUEL USING SERPENT MONTE CARLO CODE." In НАУЧНЫЙ ДИАЛОГ: ТЕОРИЯ И ПРАКТИКА. Crossref, 2025. https://doi.org/10.34660/inf.2025.35.91.131.

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Hydrogen production in severe nuclear accidents poses a significant threat to reactor safety, as exemplified by the Fukushima Daiichi disaster. This study investigates hydrogen generation in the VVER-1200 reactor under accident conditions, focusing on the zirconium-steam reaction responsible for hydrogen release in Zircaloy cladding. Using the SERPENT Monte Carlo simulation code, we model the reaction rates and hydrogen production volumes at elevated temperatures (1200°C), simulating a loss-of-coolant accident (LOCA). Results show substantial hydrogen production from the zirconium-steam reacti
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