Concept

Accident nucléaire

Publications associées (71)

Coupled 3-D Neutronics/Thermal-Hydraulics Optimization Study For Improving The Response Of A 3600 Mw(Thermal) Sfr Core To An Unprotected Loss-Of-Flow Accident

Rakesh Chawla, Konstantin Mikityuk, Aurélia Chenu, Jiri Krepel, Kaichao Sun

The sodium-cooled fast reactor (SFR), as a fast neutron spectrum system, is characterized by several performance advantages. In particular, the long-term operation of an SFR core in a closed fuel cycle will lead to an equilibrium state, where both reactivi ...

Amer Nuclear Soc2013

Application of Power Time-Projection on the Operator Splitting Coupling Scheme of the TRACE/S3K Coupled Code

Rakesh Chawla, Hakim Ferroukhi, Damar Canggih Wicaksono, Omar Zerkak

This paper reports refinement studies on the temporal coupling scheme and time-stepping management of TRACE/S3K, a dynamically coupled code version of the thermal-hydraulics system code TRACE and the 3D core simulator Simulate-3K. The studies were carried ...

American Nuclear Society2013

Effect of ion-irradiation on the microstructure and microhardness of the W-2Y(2)O(3) composite materials fabricated by sintering and hot forging

Philippe Spätig, Nadine Baluc

A W-2Y(2)O(3) material was developed in collaboration with the Plansee Company (Austria). An ingot of the material having approximate dimension of 95 mm x 20 mm was fabricated by mixing the elemental powders followed by pressing, sintering and hot forging. ...

Elsevier Science Sa2013

Optimal control for Partial Differential Equations

Antoine Giovanni Imboden

In this project report, we first present the application of the finite elements method to the numerical approximation of elliptic and parabolic PDEs over two-dimensional domains. We then consider the theory and numerical approximation of optimal control pr ...

2013

Comparative analyses of Purkinje cell gene expression profiles reveal shared molecular abnormalities in models of different polyglutamine diseases

Polyglutamine (PolyQ) diseases have common features that include progressive selective neurodegeneration and the formation of protein aggregates. There is growing evidence to suggest that critical nuclear events lead to transcriptional alterations in PolyQ ...

Elsevier Science Bv2012

Coupling a System Code with Computational Fluid Dynamics for the Simulation of Complex Coolant Reactivity Effects

Davide Bertolotto

The current doctoral research is focused on the development and validation of a coupled computational tool, to combine the advantages of computational fluid dynamics (CFD) in analyzing complex flow fields and of state-of-the-art system codes employed for n ...

EPFL2011

Spectral Broadening of Characteristic gamma-Ray Emission Peaks from C-12(He-3, p gamma)N-14 Reactions in Fusion Plasmas

Patrick Blanchard, Gabriele Grosso

The spectral broadening of characteristic gamma-ray emission peaks from the reaction C-12(He-3, p gamma)N-14 was measured in D(He-3) plasmas of the JET tokamak with ion cyclotron resonance heating tuned to the fundamental harmonic of He-3. Intensities and ...

2011

Effects of Radiation on MEMS

Herbert Shea

The sensitivity of MEMS devices to radiation is reviewed, with an emphasis on radiation levels representative of space missions. While silicon and metals generally do not show mechanical degradation at the radiation levels encountered in most missions, MEM ...

Spie-Int Soc Optical Engineering, Po Box 10, Bellingham, Wa 98227-0010 Usa2011

Nuclear material investigations by advanced analytical techniques

Manuel Alexandre Pouchon, Johannes Bertsch, Goutam Kuri

Advanced analytical techniques have been used to characterize nuclear materials at the Paul Scherrer Institute during the last decade. The analysed materials ranged from reactor pressure vessel (RPV) steels, Zircaloy claddings to fuel samples. The processe ...

Elsevier2010

Heavy-gas injection in the Generation IV gas-cooled fast reactor for improved decay heat removal under depressurized conditions

Rakesh Chawla, Konstantin Mikityuk, Aaron Simon Epiney

Decay heat removal is a key safety and design issue for the Generation IV gas (helium)-cooled fast reactor. This paper investigates the natural convection capability of the dedicated DHR loops under depressurized conditions while injecting a heavy gas into ...

Elsevier2010

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