Publications related to Isolation of a Star-Shaped Uranium(V/VI) Cluster from the Anaerobic Photochemical Reduction of Uranyl(VI)

Interaction between BaCO3 and OPC/BFS composite cements at 20 degrees C and 60 degrees C

A BaCO3 slurry, containing radioactive C-14, is produced during the reprocessing of spent nuclear fuel. This slurry is encapsulated in a Portland-blastfurnace slag composite cement. The effect of BaCO3 on the hydration of OPC and Portland-blastfurnace slag ...

Elsevier2011

Interfacial Complexation Reactions of Sr2+ with Octyl(phenyl)-N,N-diisobutylcarbamoylmethylphosphine Oxide for Understanding Its Extraction in Reprocessing Spent Nuclear Fuels

Hubert Girault, Yu Lu, Thomas James Stockmann, Zhifeng Ding

The complexation reactions between strontium (Sr2+) and octyl(phenyl)-N,N-diisobutylcarbamoylmethylphosphine oxide (CMPO) were studied at the aqueous vertical bar 1,2-dichloroethane (w vertical bar DCE) and aqueous vertical bar room-temperature ionic liqui ...

2011

Fission Rates Measured Using High-Energy Gamma-Rays from Short Half-Life Fission Products in Fresh and Spent Nuclear Fuel

Hanna Kröhnert

In recent years, higher discharge burn-ups and initial fuel enrichments have led to more and more heterogeneous core configurations in light water reactors (LWRs), especially at the beginning of cycle when fresh fuel assemblies are loaded next to highly bu ...

EPFL2011

Nuclear Energy in Europe: Uranium Flow Modeling and Fuel Cycle Scenario Trade-Offs from a Sustainability Perspective

Claudia Rebeca Binder Signer

The European nuclear fuel cycle (covering the EU-27, Switzerland and Ukraine) was modeled using material flow analysis (MFA).The analysis was based on publicly available data from nuclear energy agencies and industries, national trade offices, and nongover ...

2011

Comparative dissolution kinetics of biogenic and chemogenic uraninite under oxidizing conditions in the presence of carbonate

Rizlan Bernier-Latmani, Harish Veeramani, Jonathan Sharp

The long-term stability of biogenic uraninite with respect to oxidative dissolution is pivotal to the success of in situ bioreduction strategies for the subsurface remediation of uranium legacies. Batch and flow-through dissolution experiments were conduct ...

Elsevier2009

EQL3D: ERANOS based equilibrium fuel cycle procedure for fast reactors

Konstantin Mikityuk, Jiri Krepel

The advanced fast reactors of the fourth generation should be capable to breed their own fuel from poorly fissile 238U and to recycle the actinides from their own spent fuel. However, this recycling or actually the closure of fuel cycle has negative impact ...

Elsevier2009

Global sensitivity analysis of computer models with functional inputs

Global sensitivity analysis is used to quantify the influence of uncertain model inputs on the response variability of a numerical model. The common quantitative methods are appropriate with computer codes having scalar model inputs. This paper aims at ill ...

2009

Comparison of optimised germanium gamma spectrometry and multicollector inductively coupled plasma mass spectrometry for the determination of 134Cs, 137Cs and 154Eu single ratios in highly burnt UO2

Rakesh Chawla, Stefano Caruso, Fabian Jatuff

Non-destructive and destructive methods have been compared to validate their corresponding assessed accuracies in the measurement of 134Cs/137Cs and 154Eu/137Cs isotopic concentration ratios in four spent UO2 fuel samples with very high (52 and 71 GWd/t) a ...

Elsevier Science B.V.2008

Physicochemical Properties and Theoretical Modeling of Actinide Complexes with a para-tert-Butylcalix[6]arene Bearing Phosphinoyl Pendants. Extraction Capability of the Calixarene toward f Elements

Jean-Claude Bünzli

The coordination ability of the hexaphosphinoylated p-tert-butylcalix[6]arene

B_6bL^6

toward actinides is established, as well as its good separation ability of the actinide ions

UO_2 ^{2+}

and Th(IV) over trivalent rare earths such as La(III), Eu(III) ...

2008

Characterisation of high-burnup LWR fuel rods through gamma tomography

Stefano Caruso

Current fuel management strategies for light water reactors (LWRs), in countries with high back-end costs, progressively extend the discharge burnup at the expense of increasing the 235U enrichment of the fresh UO2 fuel loaded. In this perspective, standar ...

EPFL2007

Isolation of a Star-Shaped Uranium(V/VI) Cluster from the Anaerobic Photochemical Reduction of Uranyl(VI)

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Interaction between BaCO3 and OPC/BFS composite cements at 20 degrees C and 60 degrees C

Interfacial Complexation Reactions of Sr2+ with Octyl(phenyl)-N,N-diisobutylcarbamoylmethylphosphine Oxide for Understanding Its Extraction in Reprocessing Spent Nuclear Fuels

Fission Rates Measured Using High-Energy Gamma-Rays from Short Half-Life Fission Products in Fresh and Spent Nuclear Fuel

Nuclear Energy in Europe: Uranium Flow Modeling and Fuel Cycle Scenario Trade-Offs from a Sustainability Perspective

Comparative dissolution kinetics of biogenic and chemogenic uraninite under oxidizing conditions in the presence of carbonate

EQL3D: ERANOS based equilibrium fuel cycle procedure for fast reactors

Global sensitivity analysis of computer models with functional inputs

Comparison of optimised germanium gamma spectrometry and multicollector inductively coupled plasma mass spectrometry for the determination of 134Cs, 137Cs and 154Eu single ratios in highly burnt UO2

Physicochemical Properties and Theoretical Modeling of Actinide Complexes with a para-tert-Butylcalix[6]arene Bearing Phosphinoyl Pendants. Extraction Capability of the Calixarene toward f Elements

Characterisation of high-burnup LWR fuel rods through gamma tomography

Characterisation of high-burnup LWR fuel rods through gamma tomography

Comparison of optimised germanium gamma spectrometry and multicollector inductively coupled plasma mass spectrometry for the determination of 134Cs, 137Cs and 154Eu single ratios in highly burnt UO2

Comparative dissolution kinetics of biogenic and chemogenic uraninite under oxidizing conditions in the presence of carbonate

Interaction between BaCO3 and OPC/BFS composite cements at 20 degrees C and 60 degrees C

EQL3D: ERANOS based equilibrium fuel cycle procedure for fast reactors

Interfacial Complexation Reactions of Sr2+ with Octyl(phenyl)-N,N-diisobutylcarbamoylmethylphosphine Oxide for Understanding Its Extraction in Reprocessing Spent Nuclear Fuels

Global sensitivity analysis of computer models with functional inputs

Physicochemical Properties and Theoretical Modeling of Actinide Complexes with a para-tert-Butylcalix[6]arene Bearing Phosphinoyl Pendants. Extraction Capability of the Calixarene toward f Elements

Fission Rates Measured Using High-Energy Gamma-Rays from Short Half-Life Fission Products in Fresh and Spent Nuclear Fuel

Nuclear Energy in Europe: Uranium Flow Modeling and Fuel Cycle Scenario Trade-Offs from a Sustainability Perspective