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Apr 19 – 22, 2022
Vienna, Austria
Europe/Vienna timezone
FR22 starts in Vienna 19 - 22 April 2022 Online Stream: https://event.do/iaea/a/#/events/5048

Comparison of calculation methods for lead cooled fast reactor reactivity effects

Apr 20, 2022, 10:40 AM
12m
Vienna, Austria

Vienna, Austria

ORAL Track 6. Modelling, Simulations, and Digitilization 6.1 Neutronics

Speaker

Máté Szieberth (Budapest University of Technolgoy and Economics)

Description

The application of Generation IV reactors offers improved sustainability of nuclear energy production and extends the current reserves while it helps to reduce the amount of nuclear waste. Therefore multiple demonstrator reactor designs are now under development. In fast reactors, due to its characteristic spectra and the reactor design, the effects of the leakage is much higher, which suggest the need of transport approximations with higher angular expansion for various analysis, such as sensitivity and uncertainty analysis.
In this study three different reactivity feedback coefficient of the Advanced Lead-cooled Fast Reactor Demonstrator (ALFRED) reactor is analyzed: the coolant temperature coefficient, the cladding expansion coefficient, and the fuel temperature coefficient. During the evaluations, the central difference direct perturbation method (DPM) and the linear perturbation theory (LPT) was applied to determine the feedback coefficients and their uncertainties. Multiple codes with fundamentally different calculation methods were employed during our investigations. The continuous energy SERPENT Monte Carlo code, the multigroup TSUNAMI-3D sequence of the SCALE program package, and PARTISN discrete ordinate neutron transport code coupled with SEnTRi developed at BME was applied and the properties of these fundamentally different calculations are presented. Furthermore, uncertainty calculations were performed in order to estimate the uncertainty of the reactivity feedback coefficients due to cross-section data. In order to confirm the validity of the applied tools and methodologies, we have performed lead void coefficient calculations for the Comet critical assembly and compared the results with the published experimental data.
Our results confirm that good agreement can be reached between the different methods and with the measurement results with properly chosen calculation parameters. Besides the high level transport approximation the appropriate spatial resolution has outstanding importance in oreder to describe the high flux gradient. While Monte Carlo solutions may use more accurate geometry modeling deterministic solutions may be superior in respect to the uncertainty analysis of reactivity coefficients where small differences needs to be determined.

Affiliation/Organization Budapest University of Technology and Economics
Country/Int. organization Hungary
Speaker's title Mr
Speaker's email address szieberth@reak.bme.hu

Primary author

Zoltán István Böröczki (Budapest University of Technolgoy and Economics)

Co-authors

Ádám Aranyosy (Budapest University of Technolgoy and Economics) Máté Szieberth (Budapest University of Technolgoy and Economics)

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Paper