Publications related to Experimental investigation of moderator density variation effects in an SCWR-like fuel lattice

Improvement of the Decay Heat Removal Characteristics of the Generation IV Gas-cooled Fast Reactor

Gas cooling in nuclear power plants (NPPs) has a long history, the corresponding reactor types developed in France, the UK and the US having been thermal neutron-spectrum systems using graphite as the moderator. The majority of NPPs worldwide, however, are ...

EPFL2010

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

Rakesh Chawla, Fabian Jatuff, Michaël Plaschy, 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

Impact of new gadolinium cross sections on reaction rate distributions in 1010 BWR assemblies

Rakesh Chawla, Fabian Jatuff

Radial distributions of the total fission rate and the238U- capture-to-total-fission (C 8/F tot) ratio were measured in SVEA-96+ and SVEA-96 Optimal assemblies during the LWR-PROTEUS program. Fission rates predicted using MCNPX with JEFF-3.1 cross sections ...

American Nuclear Society2009

Interpretation of high-burnup fuel annealing tests

Rakesh Chawla, Paul Blair

The growth of the porosity in high-burnup fuel is of particular interest when considering the effect of fission gas retention within the high-burnup structure (HBS). A mechanistic model of porosity growth under annealing conditions for light water reactor ...

Atomic Energy Society of Japan2008

Three-Phase Catalytic Hydrogenation of a Functionalized Alkyne: Mass Transfer and Kinetic Studies with in Situ Hydrogen Monitoring

Albert Renken, Lioubov Kiwi, Martin Grasemann

Systematic studies of mass transfer interactions with intrinsic reaction kinetics were performed for the threephase selective hydrogenation of 2-methyl-3-butyn-2-ol (MBY) to 2-methyl-3-buten-2-ol (MBE) over a modified Pd/CaC

{O}_{3}

catalyst under solvent ...

2008

Modelling of fission gas behaviour in high burnup nuclear fuel

Paul Blair

The safe and economic operation of nuclear power plants (NPPs) requires that the behaviour and performance of the fuel can be calculated reliably over its expected lifetime. This requires highly developed codes that treat the nuclear fuel in a general mann ...

EPFL2008

Validation of Monte-Carlo simulations with measurements at the ICON beam-line at SINQ

ICON is the new cold neutron imaging facility at the neutron spallation source SINQ. The ICON facility is placed at beam-line S52 with direct view to the cold liquid D-2 moderator. The beam-line includes a 4.4 m long collimation section followed by a 1 I m ...

2008

Investigations of238U captures to total fissions in a westinghouse SVEA-96+ assembly

Rakesh Chawla, Fabian Jatuff

The reaction-rate ratio C8/Ftot, neutron captures in 238U to total fissions, has been measured in 80 out of 96 fuel rods of a Westinghouse SVEA-96+ boiling water reactor fuel assembly. High-resolution gamma spectroscopy was performed on individual fuel rod ...

American Nuclear Society2007

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

Rakesh Chawla, Filippo Tani, Fabian Jatuff, Michaël Plaschy, 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

Optimised non-invasive method to determine 238U-captures-to-total-fissions in reactor fuel

Rakesh Chawla, Fabian Jatuff

High-resolution gamma spectroscopy was performed on individual fuel rods of a fresh, highly heterogeneous Boiling Water Reactor (BWR) fuel assembly, after irradiation at low power in the PROTEUS reactor at PSI, to determine the ratio of neutron captures in ...

Elsevier2006

Experimental investigation of moderator density variation effects in an SCWR-like fuel lattice

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Improvement of the Decay Heat Removal Characteristics of the Generation IV Gas-cooled Fast Reactor

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

Impact of new gadolinium cross sections on reaction rate distributions in 1010 BWR assemblies

Interpretation of high-burnup fuel annealing tests

Three-Phase Catalytic Hydrogenation of a Functionalized Alkyne: Mass Transfer and Kinetic Studies with in Situ Hydrogen Monitoring

Modelling of fission gas behaviour in high burnup nuclear fuel

Validation of Monte-Carlo simulations with measurements at the ICON beam-line at SINQ

Investigations of238U captures to total fissions in a westinghouse SVEA-96+ assembly

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

Optimised non-invasive method to determine 238U-captures-to-total-fissions in reactor fuel

Improvement of the Decay Heat Removal Characteristics of the Generation IV Gas-cooled Fast Reactor

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

Interpretation of high-burnup fuel annealing tests

Impact of new gadolinium cross sections on reaction rate distributions in 1010 BWR assemblies

Three-Phase Catalytic Hydrogenation of a Functionalized Alkyne: Mass Transfer and Kinetic Studies with in Situ Hydrogen Monitoring

Optimised non-invasive method to determine 238U-captures-to-total-fissions in reactor fuel

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

Validation of Monte-Carlo simulations with measurements at the ICON beam-line at SINQ

Modelling of fission gas behaviour in high burnup nuclear fuel

Investigations of238U captures to total fissions in a westinghouse SVEA-96+ assembly