Publications associées à Produit de fission

Artificial Neural Networks as Surrogate Models for Uncertainty Quantification and Data Assimilation in 2-D/3-D Fuel Performance Studies

Andreas Pautz, Mathieu Hursin, Carlo Fiorina, Alessandro Scolaro, Daniel Jerôme Siefman

This paper preliminarily investigates the use of data-driven surrogates for fuel performance codes. The objective is to develop fast-running models that can be used in the frame of uncertainty quantification and data assimilation studies. In particular, da ...

2020

Data assimilation of post irradiation examination experiments to adjust fission yields

Andreas Pautz, Mathieu Hursin, Daniel Jerôme Siefman

Nuclear data, especially fission yields, create uncertainties in the predicted concentrations of fission products in spent fuel. Herein, we present a new framework that extends data assimilation methods to burnup simulations by using data from post-irradia ...

E D P SCIENCES2020

Radiation detection and energy conversion in nuclear reactor environments by hybrid photovoltaic perovskites

László Forró, Endre Horvath, Andrzej Sienkiewicz, Bálint Náfrádi, Márton Kollár, Pavao Roko Andricevic

Detection and direct power conversion of high energy and high intensity ionizing radiation could be a key element in next generation nuclear reactor safety systems and space-born devices. For example, the Fukushima catastrophe in 2011 could have been large ...

PERGAMON-ELSEVIER SCIENCE LTD2020

Nuclear data uncertainties for Swiss BWR spent nuclear fuel characteristics

Mathieu Hursin, Hakim Ferroukhi, Dimitri Rochman, Abdelhamid Dokhane, Alexander Vasiliev

The effect of nuclear data (fission yields, cross sections and emitted spectra) is quantified for spent nuclear fuel assemblies from a realistic boiling water reactor operated over 25 cycles. Nominal calculations are performed with the CASMO5, SIMULATE-3 a ...

2020

The EQL0D fuel cycle procedure and its application to the transition to equilibrium of selected molten salt reactor designs

Andreas Pautz, Jiri Krepel, Boris Aviv Hombourger

In recent years, Molten Salt Reactors (MSRs), one of the Generation IV concepts, have noticeably gained in interest. Several molten salt reactor types use fuel in liquid form, bringing various advantages, notably in terms of fuel cycle. However, simulating ...

PERGAMON-ELSEVIER SCIENCE LTD2020

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

Synthesis and Structure-Activity Relationship Studies of C2-Modified Analogs of the Antimycobacterial Natural Product Pyridomycin

Stewart Cole, Ruben Hartkoorn, Anthony Vocat

A series of derivatives of the antimycobacterial natural product pyridomycin have been prepared with the C2 side chain attached to the macrocyclic core structure by a C-C single bond, in place of the synthetically more demanding enol ester double bond foun ...

AMER CHEMICAL SOC2020

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

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Produit de fission

Artificial Neural Networks as Surrogate Models for Uncertainty Quantification and Data Assimilation in 2-D/3-D Fuel Performance Studies

Data assimilation of post irradiation examination experiments to adjust fission yields

Radiation detection and energy conversion in nuclear reactor environments by hybrid photovoltaic perovskites

Nuclear data uncertainties for Swiss BWR spent nuclear fuel characteristics

Review of kinetic modulation experiments in low power nuclear reactors

The EQL0D fuel cycle procedure and its application to the transition to equilibrium of selected molten salt reactor designs

Crosstalk between Drp1 phosphorylation sites during mitochondrial dynamics and metabolic adaptation

Power calibration methodology at the CROCUS reactor

Synthesis and Structure-Activity Relationship Studies of C2-Modified Analogs of the Antimycobacterial Natural Product Pyridomycin

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

Graph Chatbot

Chattez avec Graph Search

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

Synthesis and Structure-Activity Relationship Studies of C2-Modified Analogs of the Antimycobacterial Natural Product Pyridomycin

Crosstalk between Drp1 phosphorylation sites during mitochondrial dynamics and metabolic adaptation

The EQL0D fuel cycle procedure and its application to the transition to equilibrium of selected molten salt reactor designs

Review of kinetic modulation experiments in low power nuclear reactors

Nuclear data uncertainties for Swiss BWR spent nuclear fuel characteristics

Radiation detection and energy conversion in nuclear reactor environments by hybrid photovoltaic perovskites

Data assimilation of post irradiation examination experiments to adjust fission yields

Artificial Neural Networks as Surrogate Models for Uncertainty Quantification and Data Assimilation in 2-D/3-D Fuel Performance Studies

Power calibration methodology at the CROCUS reactor