Publications related to Fission Rates Measured Using High-Energy Gamma-Rays from Short Half-Life Fission Products in Fresh and Spent Nuclear Fuel

Power calibration methodology at the CROCUS reactor

Andreas Pautz, Vincent Pierre Lamirand, Oskari Ville Pakari, Pavel Frajtag, Axel Guy Marie Laureau

In the present article, we detail the method used to experimentally determine the power of the CROCUS zero-power reactor, and to subsequently calibrate its ex-core monitor fission chambers. Knowledge of the reactor power is a mandatory quantity for a safe ...

E D P SCIENCES2020

Development and verification of pin-by-pin homogenized simplified transport solver Tortin for PWR core analysis

Andreas Pautz, Petra Mala

Currently, the pin-by-pin homogenized solvers are a very active research field as they can, unlike the nodal codes, directly predict the local power, while requiring significantly less computational resources than the heterogeneous transport codes. This pa ...

2020

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

Aqueous effluent treatment system

Jeremy Luterbacher, Gaël Peng, Frédéric Edouard Juillard, Lionel Bertschy

Aqueous effluent treatment system (2) including a separation reactor (4) having a reactor chamber fluidly connected to an aqueous effluent source (3), connected via a pump (5) to an inlet (34) of the reactor chamber, a fluid extraction system (6) connected ...

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

The Unscented Kalman Filter: Introduction and Application to Point Reactor Kinetics

Felix Hans Michel Grimberg

This report serves two purposes. The first is to introduce the linear Kalman filter and the unscented Kalman filter to readers who are unfamiliar with either or both. To this end, it contains an extensive explanation of these methods, including all equatio ...

2020

Development and Application of Data Assimilation Methods in Reactor Physics

Daniel Jerôme Siefman

Simulations of nuclear reactor physics can disagree significantly from experimental evidence, even when the most accurate models are used. An important part of this bias from experiment is caused by nuclear data. The nuclear data have inherent uncertaintie ...

EPFL2019

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

High-Fidelity Determination of Nuclide Inventories for Radioactive Waste Disposal

Valentyn Bykov

The general license application (RBG) for the Swiss deep geological repository will be submitted in 2024. Furthermore, the decommissioning of the nuclear power plants (NPPs) is coming soon, with the Mühleberg NPP (KKM) scheduled to shut down in 2019. In su ...

EPFL2019

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

Fission Rates Measured Using High-Energy Gamma-Rays from Short Half-Life Fission Products in Fresh and Spent Nuclear Fuel

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Power calibration methodology at the CROCUS reactor

Development and verification of pin-by-pin homogenized simplified transport solver Tortin for PWR core analysis

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

Aqueous effluent treatment system

Treatment of the implicit effect in Shark-X

The Unscented Kalman Filter: Introduction and Application to Point Reactor Kinetics

Development and Application of Data Assimilation Methods in Reactor Physics

Breed-and-burn fuel cycle in molten salt reactors

High-Fidelity Determination of Nuclide Inventories for Radioactive Waste Disposal

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

Breed-and-burn fuel cycle in molten salt reactors

High-Fidelity Determination of Nuclide Inventories for Radioactive Waste Disposal

Development and Application of Data Assimilation Methods in Reactor Physics

Aqueous effluent treatment system

Power calibration methodology at the CROCUS reactor

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

Treatment of the implicit effect in Shark-X

The Unscented Kalman Filter: Introduction and Application to Point Reactor Kinetics

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

Development and verification of pin-by-pin homogenized simplified transport solver Tortin for PWR core analysis