Publications related to Iodine pit

Unmoderated molten salt reactors design optimisation for power stability

Andreas Pautz, Axel Guy Marie Laureau, Andrea Bellè

The critical region of unmoderated molten salt reactors consists in a cavity filled with a liquid fuel. The lack of internal structure implies a complex flow structure of the circulating fuel salt. A preliminary core shape optimization has been performed d ...

PERGAMON-ELSEVIER SCIENCE LTD2022

The COLIBRI experimental program in the CROCUS reactor: characterization of the fuel rods oscillator

Andreas Pautz, Vincent Pierre Lamirand, Mathieu Hursin, Carlo Fiorina, Oskari Ville Pakari, Pavel Frajtag, Axel Guy Marie Laureau, Adolfo Rais, Daniel Godat

The present article presents the mechanical characterization of the fuel rods oscillator developed for the purposes of the COLIBRI experimental program in CROCUS. COLIBRI aims at investigating the radiation noise related to fuel vibrations. The main motiva ...

2020

Validation of Monte Carlo predictions of LWR-PROTEUS safety parameters using an improved whole-reactor model

Rakesh Chawla, Fabian Jatuff, Michaël Plaschy

The recent experimental programme conducted in the PROTEUS research reactor at the Paul Scherrer Institute (PSI) has concerned detailed investigations of advanced light water reactor (LWR) fuels. More than fifteen different configurations of the multi-zone ...

Elsevier Science Ltd.2009

Development and benchmarking of a mechanical model for GFR plate-type fuel

Rakesh Chawla, Konstantin Mikityuk, Petr Petkevich

The reference fuel design currently being considered within the Generation-IV Gas-cooled Fast Reactor (GFR) project is a ceramic plate matrix with a honeycomb inner structure containing small fuel cylinders. The fuel is mixed plutonium-uranium carbide, whi ...

Elsevier Science Ltd.2009

Management of actinide waste inventories in nuclear phase-out scenarios

Rakesh Chawla, Marco Cometto

The improvement of the "radiological cleanliness" of nuclear energy is a primary goal in the development of advanced reactors and fuel cycles. The multiple recycling of actinides in advanced nuclear systems with fast neutron spectra represents a key option ...

Elsevier Ltd2008

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

Development and benchmarking of a 2D transient thermal model for GFR plate-type fuel

Rakesh Chawla, Konstantin Mikityuk, Petr Petkevich

Several new fuel designs are currently being considered within the generation-IV gas-cooled fast reactor (GFR) project. One of them, which is the GFR reference design, is a ceramic plate matrix with a honeycomb inner structure containing small fuel cylinde ...

Elsevier Science Ltd.2007

Validation of 134Cs, 137Cs and 154Eu single ratios as burnup monitors for ultra-high burnup UO2 fuel

Rakesh Chawla, Stefano Caruso, Fabian Jatuff

A measurement station has been built for the non-destructive investigation of burnt fuel rod segments through high-resolution gamma spectrometry. Four UO2 pressurised water reactor fuel rod segments with different burnup levels between 50 and 100GWd/t and ...

Elsevier2007

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Iodine pit

Atomic level insight into irradiation effects in nuclear fuel materials

Unmoderated molten salt reactors design optimisation for power stability

The COLIBRI experimental program in the CROCUS reactor: characterization of the fuel rods oscillator

Validation of Monte Carlo predictions of LWR-PROTEUS safety parameters using an improved whole-reactor model

Development and benchmarking of a mechanical model for GFR plate-type fuel

Modelling of fission gas behaviour in high burnup nuclear fuel

Management of actinide waste inventories in nuclear phase-out scenarios

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

Development and benchmarking of a 2D transient thermal model for GFR plate-type fuel

Validation of 134Cs, 137Cs and 154Eu single ratios as burnup monitors for ultra-high burnup UO2 fuel

Graph Chatbot

Chat with Graph Search

Atomic level insight into irradiation effects in nuclear fuel materials

The COLIBRI experimental program in the CROCUS reactor: characterization of the fuel rods oscillator

Unmoderated molten salt reactors design optimisation for power stability

Management of actinide waste inventories in nuclear phase-out scenarios

Validation of Monte Carlo predictions of LWR-PROTEUS safety parameters using an improved whole-reactor model

Development and benchmarking of a mechanical model for GFR plate-type fuel

Modelling of fission gas behaviour in high burnup nuclear fuel

Validation of 134Cs, 137Cs and 154Eu single ratios as burnup monitors for ultra-high burnup UO2 fuel

Development and benchmarking of a 2D transient thermal model for GFR plate-type fuel

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