Concept

Plutonium 238

Publications associées (27)

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

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

Plutonium management in the medium term

Rakesh Chawla

For many years various countries with access to commercial reprocessing services have been routinely recycling plutonium as UO2/PuO 2 mixed oxide (MOX) fuel in light water reactors (LWRs). This LWR MOX recycle strategy is still widely regarded as an interi ...

American Nuclear Society2004

Inert matrix fuel for the utilisation of plutonium

Manuel Alexandre Pouchon

Utilising fuel resources responsibly, reducing waste volume and emissions as well as conflict potentials within the international community (non-proliferation, energy demand) are among the principles for the judgment of sustainable development. Utilising a ...

Elsevier2001

Preparation of simulated inert matrix fuel with different powders by dry milling method

Manuel Alexandre Pouchon

Simulated zirconium oxide-based inert matrix fuel (IMF) has been prepared using cerium oxide replacing plutonium oxide, following the conventional pelletising route, in which an improved two-stage attrition mill was employed. Different methods have been ap ...

Elsevier1999

Comparison of pressurized water reactor core characteristics for 100% plutonium-containing loadings

Rakesh Chawla

The large quantities of reactor-grade (RG) and weapons-grade (WG) Pu accumulated worldwide could be reduced by employing 100% mixed-oxide (MOX) cores in light water reactors. The buildup of new Pu from the U present in the MOX, however remains disadvantage ...

American Nucl. Soc1998

Reactivity and Reaction Rate Ratio Changes with Moderator Voidage in a Light Water High Converter Reactor Lattice

Rakesh Chawla

Integral reaction rate ratios and other k// infinity -related parameters have been measured in the first three cores of the experimental program on light water high converter reactor (LWHCR) test lattices in the PROTEUS reactor. The reference tight-pitch l ...

American Nuclear Society1984

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