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Related publications (29)

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, Aurélia Chenu, Konstantin Mikityuk, 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

Recent progress in R&D on tungsten alloys for divertor structural and plasma facing materials

Nadine Baluc, Ho Ling Li, Antoine Cyril David Hoffmann

Tungsten materials are candidates for plasma-facing components for the International Thermonuclear Experimental Reactor and the DEMOnstration power plant because of their superior thermophysical properties. Because these materials are not common structural ...

Elsevier Science Bv2013

Thermal Simulation of Liquid-Cooled Integrated Circuits

Arvind Raj Mahankali Sridhar

Growing demands for increased functionality in consumer electronics and for information technology-enabled services in various sectors have resulted in the rise of high-performance multiprocessor system-on-chips (MPSoCs) and three-dimensionally stacked int ...

EPFL2013

A standalone decay heat removal device for the Gas-cooled Fast Reactor for intermediate to atmospheric pressure conditions

Rakesh Chawla, Konstantin Mikityuk, Aaron Simon Epiney

This paper reports a design study for a Brayton cycle machine, which would constitute a dedicated, standalone decay heat removal (DHR) device for the Generation IV Gas-cooled Fast Reactor (GFR). In comparison to the DHR reference strategy developed by the ...

Elsevier2012

Analysis of selected Phenix EOL tests with the FAST code system - Part II: Unprotected phase of the Natural Convection Test

Rakesh Chawla, Aurélia Chenu, Konstantin Mikityuk

Experimental results from the unprotected phase of the Natural Convection (NC) Test performed in the Phenix reactor in the frame of end-of-life (EOL) experiments have been used to qualify the FAST code system for Sodium-cooled Fast Reactor (SFR) transient ...

Elsevier2012

Analysis of selected Phenix EOL tests with the FAST code system - Part I: Control-rod-shift experiments

Rakesh Chawla, Aurélia Chenu, Konstantin Mikityuk

The end-of-life (EOL) tests recently performed at the Phenix reactor present a unique opportunity to validate computational tools used for Sodium-cooled Fast Reactor (SFR) static and transient analysis. In the first part of the current study, PSI's FAST co ...

Elsevier2012

Entrained liquid fraction prediction in adiabatic and evaporating annular two-phase flow

John Richard Thome, Andrea Cioncolini

A new method to predict the entrained liquid fraction in annular two-phase flow is presented. The underlying experimental database contains 2460 data points collected from 38 different literature studies for 8 different gas-liquid or vapor-liquid combinati ...

2012

Analysis of Advanced Sodium-cooled Fast Reactor Core Designs with Improved Safety Characteristics

Kaichao Sun

In order to meet the steadily increasing worldwide energy demand, nuclear power is expected to continue playing a key role in electricity production. Currently, the large majority of nuclear power plants are operated with thermal-neutron spectra and need r ...

EPFL2012

Post-irradiation analysis of the tantalum container of an ISOLDE LBE target

CERN-ISOLDE operates a range of oxides, carbides, refractory metal foils and liquid metal targets for the production of radioactive ion beams. Following irradiation with a pulsed beam of 1 GeV and 1.4 GeV protons at temperatures reaching 600 degrees C, the ...

Elsevier Science Bv2012

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