Publications de Flavio Dante Giust

Experimental Validation of 3-D Reconstructed Pin Power Distributions in Full-Scale BWR Fuel Assemblies with Partial-Length Rods

Total fission rate measurements have been performed on full-size boiling water reactor fuel assemblies of type SVEA-96 Optima2 in the framework of phase III of the light water reactor (LWR)PROTEUS experimental program at Paul Scherrer Institute. This paper ...

Amer Nuclear Soc2013

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

Flavio Dante Giust

The present doctoral research aims at the appraisal of nodal core simulators used for the calculation of commercial boiling water reactor (BWR) cores, against measurements carried out at the Paul Scherrer Institute under the LWR-PROTEUS experimental progra ...

EPFL2012

Experimental Comparisons of 3D Reconstructed Pin-Power Distributions in Full-Scale BWR Fuel Assemblies

Rakesh Chawla, Flavio Dante Giust

In this paper, reconstructed local fission rates obtained with the two-group nodal diffusion program PRESTO-2, used at the Leibstadt Nuclear Power Plant (KKL) in Switzerland, are compared with experimental results and MCNPX calculations. The experimental f ...

2011

Experimental validation of radial reconstructed pin-power distributions in full-scale BWR fuel assemblies with and without control blade

Rakesh Chawla, Flavio Dante Giust

Total fission rate measurements have been performed on full-size BWR fuel assemblies of type SVEA-96+ in the zero power reactor PROTEUS at the Paul Scherrer Institute. This paper presents comparisons of reconstructed 2D pin fission rates from nodal diffusi ...

Elsevier2010

Experimental validation of reaction rate distributions for a SVEA-96+ BWR assembly with hafnium control blades

Michaël Plaschy, Rakesh Chawla, Fabian Jatuff, Flavio Dante Giust

The accurate estimation of reactor physics parameters related to the presence of cruciform absorber blades in boiling water reactors (BWRs) is important for safety assessment and for achieving flexible operation during the cycle. Characteristics that are a ...

Atomic Energy Society of Japan2009

Void reactivity coefficient benchmark results for a 10x10 BWR assembly in the full 0-100% void fraction range

Rakesh Chawla, Fabian Jatuff, Flavio Dante Giust

A boiling water reactor SVEA-96+ fresh fuel lattice has been used as the basis for a benchmark study of the void reactivity coefficient at assembly level in the full voidage range. Results have been obtained using the deterministic codes CASMO-4, HELIOS, P ...

Elsevier Science Ltd.2009

Comparisons of deterministic neutronic calculations with Monte Carlo results for an advanced BWR fuel assembly with hafnium control blades

Michaël Plaschy, Rakesh Chawla, Fabian Jatuff, Filippo Tani, Flavio Dante Giust

From the neutronic viewpoint, the optimization of BWR core designs is strongly related to the accurate determination of flux variations inside and around fuel assemblies. These fluctuations, which are mainly due to the high heterogeneity of the fuel and mo ...

Atomic Energy Society of Japan2006

Effects of void uncertainties on the void reactivity coefficient and pin power distributions for a 1010 BWR assembly

Rakesh Chawla, Fabian Jatuff, Flavio Dante Giust

An important source of uncertainty in boiling water reactor physics is associated with the precise characterisation of the moderation properties of the coolant and by-pass regions, with significant impact on reactor physics parameters such as the lattice n ...

Elsevier2006