Publications related to Systematic Sensitivity and Uncertainty Analysis of Sodium-Cooled Fast Reactor Systems

Uncertainty and sensitivity analysis of PWR mini-core transients in the presence of nuclear data uncertainty using non-parametric tolerance limits

Andreas Pautz, Winfried Zwermann, Alexander Aures

The impact of nuclear data uncertainties is studied for the reactor power and the reactivity during control rod withdrawal transients with reactivity insertions of 0.5

and 0.97

, respectively, for a PWR mini-core model. Multi-group cross sections, the mul ...

PERGAMON-ELSEVIER SCIENCE LTD2020

Uncertainty propagation for the design study of the PETALE experimental programme in the CROCUS reactor

Andreas Pautz, Vincent Pierre Lamirand, Dimitri Rochman, Axel Guy Marie Laureau

The PETALE experimental programme in the CROCUS reactor intends to provide integral measurements to constrain stainless steel nuclear data. This article presents the tools and the methodology developed to design and optimize the experiments, and its operat ...

2020

Treatment of the implicit effect in Shark-X

Mathieu Hursin, Hakim Ferroukhi, Alexander Vasiliev

Shark-X is a set of Perl-based tools build around the deterministic neutron transport code CASMO-5, used to perform uncertainty quantification for lattice calculations at the Paul Scherrer Institut (PSI). While perturbing an input parameter, e.g. a cross s ...

2020

Uncertainty propagation based on correlated sampling technique for nuclear data applications

Andreas Pautz, Vincent Pierre Lamirand, Dimitri Rochman, Axel Guy Marie Laureau

A correlated sampling technique has been implemented to estimate the impact of cross section modifications on the neutron transport and in Monte Carlo simulations in one single calculation. This implementation has been coupled to a Total Monte Carlo approa ...

2020

On data assimilation with Monte-Carlo-calculated and statistically uncertain sensitivity coefficients

Andreas Pautz, Mathieu Hursin, Daniel Jerôme Siefman

Sensitivity coefficients from Monte Carlo neutron transport codes have uncertainties that can affect nuclear data adjustments with integral experiments. This paper presents an extended version of Generalized Linear Least Squares (GLLS), called xGLLS, that ...

PERGAMON-ELSEVIER SCIENCE LTD2020

Design Concept and Thermal & x2013;Mechanical Analysis of the Optical Mirror (M3) for the ITER ECH Upper Launcher

Timothy Goodman, René Chavan

The mirror M3 is a part of the in-vessel quasi-optical beam propagation system for the ITER electron cyclotron heating upper launcher (ECHUL). The millimeter waves are guided through fixed mirror sets (M1, M2, and M3) and the front steering mirror set (M4) ...

IEEE-INST ELECTRICAL ELECTRONICS ENGINEERS INC2020

Reactor simulations with nuclear data uncertainties

Andreas Pautz, Winfried Zwermann, Friederike Bostelmann, Alexander Aures

The paper demonstrates the influence of uncertainties in microscopic nuclear data on the results of reactor simulations, both for stationary and transient states. It gives an overview on the methods in use for uncertainty and sensitivity analyses with resp ...

ELSEVIER SCIENCE SA2019

Breed-and-burn fuel cycle in molten salt reactors

Andreas Pautz, Jiri Krepel, Boris Aviv Hombourger

The operation of a reactor on an open but self-sustainable cycle without actinide separation is known as breed-and-burn. It has mostly been envisioned for use in solid-fueled fast-spectrum reactors such as sodium-cooled fast reactors. In this paper the app ...

EDP Sciences2019

Application of multiphysics model order reduction to doppler/neutronic feedback

Carlo Fiorina

In this paper, a proper orthogonal decomposition based reduced-order model is presented for parametrized multiphysics computations. Our application physics is Doppler feedback in a simplified model of the molten salt fast reactor concept. The reduced model ...

EDP Sciences2019

Determination of the activity inventory and associated uncertainty quantification for the CROCUS zero power research reactor

Andreas Pautz, Mathieu Hursin, DongHyuk Lee

The paper describes the source term estimation of CROCUS, the zero power research reactor of EPFL, to be used for dispersion analysis under accidental conditions. To fulfil regulatory requirements, the source term of the CROCUS fuel is estimated through Mo ...

2019

Systematic Sensitivity and Uncertainty Analysis of Sodium-Cooled Fast Reactor Systems

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Uncertainty and sensitivity analysis of PWR mini-core transients in the presence of nuclear data uncertainty using non-parametric tolerance limits

Uncertainty propagation for the design study of the PETALE experimental programme in the CROCUS reactor

Treatment of the implicit effect in Shark-X

Uncertainty propagation based on correlated sampling technique for nuclear data applications

On data assimilation with Monte-Carlo-calculated and statistically uncertain sensitivity coefficients

Design Concept and Thermal & x2013;Mechanical Analysis of the Optical Mirror (M3) for the ITER ECH Upper Launcher

Reactor simulations with nuclear data uncertainties

Breed-and-burn fuel cycle in molten salt reactors

Application of multiphysics model order reduction to doppler/neutronic feedback

Determination of the activity inventory and associated uncertainty quantification for the CROCUS zero power research reactor

Uncertainty and sensitivity analysis of PWR mini-core transients in the presence of nuclear data uncertainty using non-parametric tolerance limits

Uncertainty propagation for the design study of the PETALE experimental programme in the CROCUS reactor

Reactor simulations with nuclear data uncertainties

Treatment of the implicit effect in Shark-X

Uncertainty propagation based on correlated sampling technique for nuclear data applications

On data assimilation with Monte-Carlo-calculated and statistically uncertain sensitivity coefficients

Design Concept and Thermal & x2013;Mechanical Analysis of the Optical Mirror (M3) for the ITER ECH Upper Launcher

Breed-and-burn fuel cycle in molten salt reactors

Application of multiphysics model order reduction to doppler/neutronic feedback

Determination of the activity inventory and associated uncertainty quantification for the CROCUS zero power research reactor