Preliminary neutronics analysis for generation III+ VVER design - VVER-1200

Thilagam, L.; Mohapatra, D.K.

doi:10.1016/j.nuclphysbps.2023.10.002

Cited by 3 publications

(1 citation statement)

References 3 publications

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“…Because of its low parasitic neutron absorption, zirconium alloy fuel cladding has been widely used since the inception of commercial nuclear power plants (Thilagam and Mohapatra, 2023). However, in a design-based accident scenario, a condition may result in a reduction in safety margins.…”

Section: Introductionmentioning

confidence: 99%

Accident Tolerant Fuel Cladding Materials for Light Water Reactors: Analysis of Neutronic Characteristics

Aziz,

Rivai,

Panitra

et al. 2024

IJTech

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Nuclear reactor fuel is the basic component of all safety requirements associated with nuclear energy production. The neutronic characteristics of light water reactors with candidate accident-tolerant fuel cladding materials were investigated in this work to improve nuclear safety. The materials were chosen for their high-temperature strength, radiation resistance, and corrosion resistance, which will contribute to nuclear safety. The research was conducted using a deterministic neutronic code for reactor design and analysis. The neutronic properties of a light water reactor system with candidate cladding materials were analyzed and compared to those of the reference. The reference cladding material was Zircaloy-4, and the candidate fuel cladding materials examined were FeCrNi alloy, oxide dispersion strengthened steels of FeCrY2O3 and FeCrZrO2. The eigenvalues of the reactor were computed at various fuel temperatures and burnup stages. The results of the study revealed that employing candidate cladding materials led to a slightly hardened neutron spectrum, reducing initial excess reactivity and resulting in lower fuel burnup. This can be compensated by adding fuel enrichment up to 6%., which yields burnup value of 42000 MWd/T, which is higher than the reference of 40000 MWd/T with a reduced gap in initial excess reactivity from 28.4% to 25.4%. The candidate fuel cladding materials also showed better than reference reactivity loss properties in case of unwanted temperature increase. This demonstrated that the examined improved tolerant materials have the ability to increase the inherent safety of nuclear reactors.

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Section: Introductionmentioning

confidence: 99%

Accident Tolerant Fuel Cladding Materials for Light Water Reactors: Analysis of Neutronic Characteristics

Aziz,

Rivai,

Panitra

et al. 2024

IJTech

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Automated group constant parameterization for low sample sizes using different Machine learning approaches

Sebestény,

Panka,

Batki

2024

Annals of Nuclear Energy

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Nonlinear system dynamics simulation of thermal processes in the VVER-1200 reactor core

Salman,

Louis

2024

Kerntechnik

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This study presents developing and validating a nonlinear dynamic model for simulating thermal processes in the VVER-1200 reactor core, a third-generation pressurized water reactor with enhanced safety features and improved thermal efficiency. The model employs a point kinetic mathematical approach, incorporating key neutronic parameters extracted from previous analyses of the VVER-1200 under normal operating conditions. These parameters, including neutron flux distribution, power peaking factors, and reactivity coefficients, were integrated into the reactor kinetic model to capture complex feedback mechanisms. In this study, the variation of reactor power with control rod insertion is examined under normal operating conditions. The analysis focuses on how different levels of control rod insertion influence reactor performance, providing insights into optimizing operational efficiency and safety. Monte Carlo code MCNP6 was used to estimate neutronic and kinetic parameters for the proposed model. The model’s validation involved comparing simulation results against detailed Monte Carlo N-Particle calculations, specifically focusing on power changes due to reactivity variations induced by control rod movements. Results showed strong agreement between the nonlinear dynamic model and MCNP calculations. The validated model provides valuable insights into the VVER-1200 core’s thermal behavior under steady-state and transient conditions. It can investigate critical hot spots, identify thermal limits, and assess system perturbation responses. The model’s computational efficiency makes it a practical tool for further optimization and safety analyses of the VVER-1200 design.

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Preliminary neutronics analysis for generation III+ VVER design - VVER-1200

Cited by 3 publications

References 3 publications

Accident Tolerant Fuel Cladding Materials for Light Water Reactors: Analysis of Neutronic Characteristics

Accident Tolerant Fuel Cladding Materials for Light Water Reactors: Analysis of Neutronic Characteristics

Automated group constant parameterization for low sample sizes using different Machine learning approaches

Nonlinear system dynamics simulation of thermal processes in the VVER-1200 reactor core

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