Publications associées à Little Boy

Neutron-Gamma Noise Measurements in a Zero-Power Reactor Using Organic Scintillators

Andreas Pautz, Vincent Pierre Lamirand, Oskari Ville Pakari

Noise measurements in light water reactor systems aid in generating validation data for integral point kinetic parameter predictions and generating monitoring parameters for reactor safety and safeguards. The CROCUS zero-power reactor has been used to supp ...

Ieee-Inst Electrical Electronics Engineers Inc2024

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

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

Thermal-hydraulic and quench analysis of the DEMO toroidal field winding pack WP1

Pierluigi Bruzzone, Kamil Sedlák

Three alternative designs of the toroidal field (TF) coil were proposed for the European DEMO being developed under the Eurofusion Consortium. The most ambitious TF coil winding pack in terms of technological deviation from the ITER TF coil design and cons ...

ELSEVIER2017

Characterization of solvent-filled polyurethane/urea-formaldehyde core-shell composites

Véronique Michaud, Sam Neuser, Erica Manfredi

Encapsulation of liquid phases is a crucial step in many self-healing material systems where a healing agent has to be protected during processing and then released during a damage event. In this work, the mechanical properties of polyurethane (PU) reinfor ...

Elsevier2014

Study of Nuclear Decay Data Contribution to Uncertainties in Heat Load Estimations for Spent Fuel Pools

Andreas Pautz, Mathieu Hursin, Hakim Ferroukhi, Alexander Vasiliev

At the Paul Scherrer Institut (PSI), a methodology for nuclear data uncertainty propagation in CASMO-5M (C5M) assembly calculations is under development. This paper presents a preliminary application of this methodology to C5M decay heat calculations. Appl ...

Academic Press Inc Elsevier Science2014

Application of the PSI-NUSS Tool for the Estimation of Nuclear Data Related k(eff) Uncertainties for the OECD/NEA WPNCS UACSA Phase I Benchmark

Andreas Pautz, Hakim Ferroukhi, Tiankai Zhu, Alexander Vasiliev

At the Paul Scherrer Institute (PSI), a methodology titled PSI-NUSS is under development for the propagation of nuclear data uncertainties into Criticality Safety Evaluation (CSE) with the Monte Carlo code MCNPX. The primary purpose is to provide a complem ...

Academic Press Inc Elsevier Science2014

Improved gamma-heating calculational methods for fast reactors and their validation for plutonium-burning configurations

Rakesh Chawla, Gérald Rimpault

A new calculational scheme has been developed for the accurate assessment of gamma heating in fast reactors, its special feature being the determination of the gamma source distribution that is formulated in a near-to-exact manner. The improved methodology ...

American Nuclear Society2001

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Little Boy

Neutron-Gamma Noise Measurements in a Zero-Power Reactor Using Organic Scintillators

Data assimilation of post irradiation examination experiments to adjust fission yields

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

Thermal-hydraulic and quench analysis of the DEMO toroidal field winding pack WP1

Shape-Selective Assembly of Anisotropic, Deformable Microcomponents Using Bottom-Up Micromanufacturing

Characterization of solvent-filled polyurethane/urea-formaldehyde core-shell composites

Study of Nuclear Decay Data Contribution to Uncertainties in Heat Load Estimations for Spent Fuel Pools

Application of the PSI-NUSS Tool for the Estimation of Nuclear Data Related k(eff) Uncertainties for the OECD/NEA WPNCS UACSA Phase I Benchmark

Appraisal of Core Analysis Methods against Zero-Power Experiments on Full-Scale BWR Fuel Assemblies

Improved gamma-heating calculational methods for fast reactors and their validation for plutonium-burning configurations

Graph Chatbot

Chattez avec Graph Search

Neutron-Gamma Noise Measurements in a Zero-Power Reactor Using Organic Scintillators

Data assimilation of post irradiation examination experiments to adjust fission yields

Thermal-hydraulic and quench analysis of the DEMO toroidal field winding pack WP1

Characterization of solvent-filled polyurethane/urea-formaldehyde core-shell composites

Study of Nuclear Decay Data Contribution to Uncertainties in Heat Load Estimations for Spent Fuel Pools

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

Appraisal of Core Analysis Methods against Zero-Power Experiments on Full-Scale BWR Fuel Assemblies

Shape-Selective Assembly of Anisotropic, Deformable Microcomponents Using Bottom-Up Micromanufacturing

Application of the PSI-NUSS Tool for the Estimation of Nuclear Data Related k(eff) Uncertainties for the OECD/NEA WPNCS UACSA Phase I Benchmark

Improved gamma-heating calculational methods for fast reactors and their validation for plutonium-burning configurations