Concept

Plutonium

Publications associées (75)

Fabrication and microstructure characterization of inert matrix fuel based on yttria stabilized zirconia

The deployment of a suitable, Pu-bearing inert matrix fuel (IMF) could offer an attractive option as a single-recycling LWR strategy aimed at reducing the currently growing plutonium stockpiles. A development programme focusing on yttria stabilized zirconi ...

Elsevier2005

Promoting or preventing haloaryllithium isomerizations: differential basicities and solvent effects as the crucial variables

Christophe Heiss, Thierry Rausis

Deprotonation-triggered heavy halogen migrations should become a favorite tool in arene synthesis if their occurrence and outcome could be made predictable. Particularly attractive, though extremely rare, are stop-and-go situations where a first intermedia ...

2005

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

Adapting and applying SPECT to the investigation of reaction rate distributions within lightly activated nuclear fuel pins

Rakesh Chawla, Fabian Jatuff

Single Photon Emission Computerised Tomography, a non-destructive imaging technique particularly employed for medical diagnoses, has been adapted and applied for the first time to the study of two-dimensional reaction rate distributions within lightly acti ...

Elsevier2004

Zirconium nitride as inert matrix for fast systems

Manuel Alexandre Pouchon, Marco Streit

Zirconium nitride has been proposed as inert matrix material to burn plutonium or to transmute long-lived actinides in accelerator-driven sub-critical systems or fast reactors. In combination with the possibility to fabricate specially shaped fuel pellets, ...

Elsevier2003

The effect of nuclear data on the MCNPX modeling of moderator level variations in the CROCUS critical facility

Rakesh Chawla

A detailed MCNPX (version 2.4.0) model of the CROCUS zero-power critical facility was used to investigate the effect of nuclear data on the analysis of reactivity perturbations caused by variations in the moderator level. The analysis was performed using t ...

Atomic Energy Society of Japan2003

Cermet sphere-pac concept for inert matrix fuel

Manuel Alexandre Pouchon

In the inert matrix fuel concept, plutonium reprocessed from spent fuel is burned in an inert matrix, e.g. yttria-stabilized zirconia. Coming from wet reprocessing, the internal gelation can perform an easy micro-spheres production. Utilization of these pa ...

Elsevier2003

Interpretation of experimental results from moderate-power in-pile testing of a Pu-Er-Zr-oxide inert matrix fuel

Rakesh Chawla

Pu-Er-Zr oxide as an inert matrix fuel (IMF) could be an attractive option for a once-through LWR strategy aimed at reducing the currently growing plutonium stockpiles. A basic question related to the practical introduction of such an IMF into a current-da ...

Elsevier2003

Development of Sphere-Pac Nuclear Fuel Behavior Analysis Code

Manuel Alexandre Pouchon

In the feasibility study of a FBR cycle system, alternative nuclear fuels are considered. One option is the "sphere-pac" fuel, which consists of a spherical particle bed vibro-packed into the cladding tube. Potential advantages of this concept are an almos ...

2002

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

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